ML20246B199
| ML20246B199 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 06/30/1989 |
| From: | Mckibben J, Meyer W MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8908230279 | |
| Download: ML20246B199 (314) | |
Text
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Research' Reactor Facility UNIVERSITY OF MISSOURI g,,,,,cn g,,g August 16, 1989 columbia. Missouri es211 Telephone (314) 882-4211
- Usi,w - 40k'ter U. S. Nuclear Regulatory Commission Standardization & Non-Power Reactor Project Directorate Office of Nuclear Reactor Regulation Mail Station P1-137 Washington, D. C. 20555 ATTENTION: Document Control Desk
REFERENCE:
Docket 50-186 University of Missouri Research Reactor License R-103
SUBJECT:
Annual Report as required by Technical Specification 6.1.h(4).
Dear Sir:
Enclosed is a copy of the Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers 1 July 1988 through 30 June 1989.
If you have have questions, please feel free to call.
S ncerely, WMt Walt A. Meyer, .
Reactor Manager Enclosure (1)
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8908230279 890630 PDR ADOCK 05000186 R PDC
l UNIVERSITY OF MISSOURI lI I.
- s. UNilVERSITY OF M SSOURL g RESEARCH REACTOR I
- g OPERATIONIS ANNUAL RE3 ORT 1988-1989 I
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Uf;IVERSITY OF MISSOURI RESEARCH REACTOR FACILITY I REACTOR OPERATIONS ANNUAL REPORT w
AUGUST 1989 I
I Compiled by the Reactor Staff Submitted by a Walt A. Meyer, Jr
, jg Reactor !!anager I aeviewed and Approved p
l /,r 2C%dk, J. C. ficKibben Associate Director
'g.
g TABLE OF CONTENTS Section Pa g Number
- 1. REACTOR OPERATIONS
SUMMARY
. . . . . . . . . . . . 1-1 through 18
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II. CHANGES TO THE STANDARD OPERATING PROCEDURES . . . . . . . . . . . . . . . . . . . . 11-1 through 3
- I l 111-1 only l 111. REVISIONS TO THE HAZARDS
SUMMARY
REPORT .....
f IV. PLANT AND SYSTEM MODIFICATIONS . . . . . . . . . . IV-1 through 2 V. NEW TESTS AND EXPERIMENTS ............ V-1 through'2 VI. SPECI AL NUCLEAR MATERI AL ACTIVITIES ....... VI-1 through E Vll. REACTOR PHYSICS ACTIVITIES . . . . . . . . . . . . Vll-1 through 5 Vill.
SUMMARY
OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT . . . . . . . . . . . Vill-1 through 3 IX.
SUMMARY
OF ENVIRONMENTAL SURVEYS . . . . . . . . . IX-1 through 10 I X.
SUMMARY
OF RADIATION E"POSURES TO FACILITY STAFF, EXPERIMENTERS, AND VISITORS . . . . . . . X-1 through 2 I
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SECTION I l
REACTOR OPERATIONS
SUMMARY
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.g E 1 July 1988 through 30 June 1989 The following table and discussion summarize reactor operations in the period l' July 1988 through 30 June 1989.
Full Power Percent
- Date Full Power Hours Megawatt Days of Total Time of Schedule July 1988 702.2 292.91 94.36 105.71 Aug. 1988 670.8 279.68 90.16 100.98 Sept.1988 630.E 263.02 87.61 98.12 Oct. 1988 697.8 290.79 93.68 104.90 Nov. 1988 647.2 270.02 89.89 100.68 Dec. 1988 650.1 271.10 87.38 97.86 Jan. 1989 681.5 284.11 91.60 102.59 Feb. 1989 620.7 . 258.69 92.37 103.45 Mar. 1989 681.2 283.94 91.56 102.55 Apr. 1989 612.8 255.47 85.23 95.46 May 1989 669.4 279.02 89.97 100.77 June 1939 633.3 266.33 88.65 99.29 Total for Year 7902.8 3295.08 90.21% of 101.04% of time for sched. time yr. at 10MW for yr. at 10 MW
- MURR is scheduled to average at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> per week at 10MW.
Total time is the number of hours in a month or year.
There were 45 unscheduled shutdowns recorded during the year 1 July 1988 through June 30, 1989. Of these shutdowns, 23 were Rod Run-ins (RRIs) and 22 were scrams.
Twenty two of the unscheduled shutdowns (8 RRIs, 14 scrams) were due to NI drawer, detector or detector cabling failure generating a spurious shutdown signal (no actual high power or short period indicated). Many of the spurious shutdowns I-1
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c were coincident with the annunciator receiving and clearing the 95% downscale l trip for the NI instruments. The Electronics Technicians confirmed that a 1
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ground loop existed in the NI system when the channel #4 detector intermittently ]
I grounded against its drywell. An anodized detector sleeve has been manuf actured j to increase the resistance between the channel #4 detector and ground. The DC power supply cables to the NI system were also found to be degraded due to heat and age and have been replaced.
- Of the remaining unscheduled shutdowns, nine were manually initiated by the duty operator in order to repair equipment, eight were due to personnel errors and two were due to loss of electrical power to the Facility.
JULY 1988 The reactor operated continuously in July with the following exceptions:
I four shutdowns fo scheduled maintenance and one unscheduled shutdown.
On July 19, a reactor scram and isolation occurred due to high radiation detected by the reactor bridge and exhaust air plenum' radiation monitors. All l personnel exited the containment building per procedure and remained outside until health physicists cleared the containment building for re-entry after checking radiation levels from the remote station and performing a walk-through survey.
The scram and isolation occurred when a Reactor Services' technician raised a neutron detector experiment to within several feet of the pool surface in an attempt to obtain a lower neutron flux indication. This action was counter to previous instructions not to move the detector experiment without operator assistance. The reactor bridge radiation monitor. tripped when the radiation level at the pool surface reached 50 mR/hr. The detector experiment was immediately lowered to a secure position and all personnel exited the contain-ment building.
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iI The technician involved was no longer allowed to work on experiments in the reactor pool. The reactor was then refueled and returned to normal operation.
Major maintenance items for July included replacing detectors for nuclear instrument channels #4 and #5.
AUGUST 1988 The reactor operated continuously in August with the following exceptions:
four shutdowns for scheduled maintenance; and six unscheduled shutdowns.
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On August 10 and again on August 31, a rod not in contact with magnet rod l run-in occurred when control blade "A" separated from its raagnet during routine shimmi ng. In both cases, control blade "A" was being withdrawn to near its upper travel limit of 26 inches. Af ter inspection of the anvil, magnet and j guide tube alignment, the-blade was manually pull tested and was found to have a slight increase in pull weight between 25 and 26 inches. The cause for this was f
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- determin?d to be bearing roughness in the upper inch of travel on this offset mechanism. This particular control blade offset was replaced September 8,1988 as part of its normal two year cycle. f On August 10, after reaching criticality during a normal startup, the shift supervisor initiated a manual rod run-in to take the reactor subcritical as per Standard Operating Procedure in order to resolve a discrepancy between the esti-mated critical position (ECP) and the actual critical oanked rod position. The l
I reactor physicist concluded that he had failed to consider the Xenon contribu- ~i tion of two fuel elements in this core which had been used in the previous core.
Once the Xenon concentration from the two fuel elements were included in the ECP l calculation, the differential between the ECP and the actual critical rod position was within accepted limits and the startup continued with no further problems.
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On August 11, after reaching critical during a normal startup, the shift supervisor again initiated a manual rod run-in to resolve uncertainties about the flux trap reactivity worth. After consultation with the reactor physicist, the reactor was shutdown, the flux trap was removed and the strainer was instal-led. A startup to criticality was then performed to determine critical rod-bank
' position with the flux trap removed. This measurement indicated that the flux trap reactivity worth was within technical specification limits and that the initial prestartup uncorrected ECP estimate was too high. A normal startup was then completed with no further problems.
On August 23, a reactor loop low flow scram occurred. .No ' actual low flow condition was indicated on any instrumentation. A subsquent compliance check on reactor loop flow transmitters 912A and 912E found the "A" loop scram set 50 gpm too high. The normal flow maintained per loop is 1830 to 1850 gpa (Techni-cal Specification limit is 1625 gpm/ loop). The scram setpoint is conservatively set at 1725 + 25 gpm. In this instance, the scram setpoint was 1790, close enough to normal flow that spurious variations in flow initiated the scram.
This scram setpoint was reset to the proper position and the transmitter was ,
tested satisf actorily. The reactor was then refueled and returned to normal operation. The scraa setpoint was checked on each of two subsequent maintenance days to ensure it was not drifting.
On August 31, a manual scram was initiated by the duty operator when a ladder being carried in by a painter became lodged in the outer personnel air-lock door, rendering it inoperatle. The door safety edge failed to function properly and allowed the door to close on the ladder. The safety edge and its connecting cable were replaced and tested satisfactorily. The reactor was then returned to normal operation.
Major maintenance items for August included: replacing N. I. channel 5/6 chart drive motor; repairing the manual clutch on the outer airlock door; I-4 I
replacing N.1. channel #3 detector; and replacing the safety edge and its con-necting cable on the outer personnel airlock door.
I SEPTEMBER 1988 The reactor operated continuously in September with the following excep-tions: four shutdowns for scheduled maintenance and five unscheduled shutdowns.
On September 8, a rod not in contact with magnet rod run-in occurred when control blade "D" disengaged from its magnet during a normal reactor startup.
The lower guide tube housing was realigned and the anvil surf ace was cleaned.
A normal reactor startup was then completed with no further problems.
On September 16, a nuclear instrument channel #6 high power rod run-in occurred when the reactor was placed in auto control with the power level set meter indication approximately 8% higher than the wide range monitor (channel #4)
I indication.
i This occurred after the wide range monitor drawer amplifier feed-I back potentiometer had been adjusted to indicate a lower reading. The operators failed to lower the power level set meter indication to approximately 3% below the #4 indication as called for by procedure. The rod run-in was caused when the wide range monitor servo unit called for a regulating blade withdrawal to make up the difference between the power level set meter indication and channel _
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- 4 indication. This action raised channel #6 indication to 114% (actual power was calculated to be 10.94 MW) which resulted in the rod run-in. The rod run-in was reset, the power level set was lowered to the proper position and the reac-tor was returned to normal- operation. The operators involved were instructed to follow proper procedure.
On September 21, a channel #4 high power rod run-in occurred several min-utes after a cooling tower fan had been shifted from slow to fast speed during
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normal operations. The increased cooling resulting from the fan shift lowered the primary temperature. Normally the regulating blade would automatically be I-5
inserted to counteract the subsequent reactivity addition. However, the regu-lating blade failed to respond in the aatomatic mode which resulted in an increase in the power range nuclear instrument indications and the subsequent rod run-in. The duty operator reset the rod run-in but found that the regu-lating blade would not respond in manual or automatic control. The reactor was then shut down to determine the reason for the regulating blade failure. The problem was determined to be a loose set screw in the regulating blade reducer coupling which caused.a failure of the drive mechanism. Electronics technicians
- replaced the coupling and the reactor was refueled and returned to normal opera-tions. The details of the regulating blade failure were reported in a Licensee Event Report dated October 19, 1988.
On September 29, a manual scram war initiated when the duty operator observed that nuclear instrument channel #3 (Intermediate Range Monitor) had failed downscale during normal operation. The detector and cables for channel
- 3 were rep'.ded and tested satisfactorily and returned to operation. The
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details of this nuclear instrument failure and the corrective actions taken were reported in a Licensee Event Report dated October 28, 1988.
Later on September 29, a manual scram was initiated by the shift supervisor 20 minutes after a normal startup when he observed that there was a 10 tempera-ture discrepancy between primary heat exchange RTD's 980A and 980B. The con-nections to the RTD's for 980A and 980B were checked for looseness or oxidation.
These connections had been disconnected as part of Compliance Check CP-8B earlier in the day, September 29. The calibration of the RTD's were checked satisfactorily and after reconnecting the leads the 980A and 980B indications -
were in close agreement. The reactor was returned to normal operation. The details and corrective actions taken with respect to this temperature dis-crepancy were reported in a Licensee Event Report dated October 28, 1988.
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Major maintenance items for September included: performing the biennial changeout of control blade offset "A"; rebuilding the 16 inch exhaust isolation valve "A"; completing the removal of the "N-6" and "P-6" irradiation wedges and installation of graphite reflector assemblies "SA" and "6-C: in their positions;.
replacing the regulating blade reducer coupling: removing "L-6" irradiation wedge and installing graphite wedge "5-C"; replacing channel #3 detector and cables; reinstalling the "N-6" irradiation wedge in "N" position; and replacing graphite wedge "5-C" with wedge "5-A".
OCTOBER 1988 The reactor operated continuously in October with the following exceptions:
four shutdowns for scheduled maintenance. There were no unscheduled shutdowns.
During the month, Nuclear; Regulatory Commission inspectors performed unannounced inspections of Emergency Planning, Physical Security and Special i
Nuclear Material accountability.
One major maintenance evolution completed in October was the painting of the containment building internal surface with an impermeable compound. Con-struction commenced on a building addition to house a new emergency generator.
Plans were finalized regarding modifications to the Facility ventilation exhaust system.
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The reactor operated continuously in November with the following excep-tions: four shutdowns for scheduled maintenance and five unscheduled shutdowns.
On November 9, a power level interlock scram occurred when the-solenoid for valve 546-B failed. Valve 546-B is one of the two (redundant) in-pool convec-tion cooling loop valves which opens on loss of primary coolant. The failure of the solenoid caused the valve to fail open which permitted coolant bypass flow around the core. The resulting reduction in core flow was sensed by core aP l-7 t___.~_________.________ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ . ,
I pressure sensor 929, which immediately initiated the scram. The primary and pool coolant systems remained in operation, providing normal cooling after the shutdown. The solenoid was replaced and the reactor was refueled and returned to normal operation.
On November 11, a nuclear instrument anomaly scram occurred when the detector for the nuclear instrument power range monitor (channel #5) failed.
The detector was replaced and tested satisfactorily and the reactor was refueled and returned to normal operation. _
l On November 20, a manual rod Pun-in was initiated when the regulating blade was observed to be slower than normal responding to decreases in reactor power in its automatic mode. Subsequent investigation revealed that the ball plunger which provides the mechanical linkage between the regulating rod drive gear box This loose connection allowed andballlscrewhadloosenedduetovibrations.
the gear' box output shaft to slip under the load of lifting the regulating blade and offset arm but it did not slip lowering the regulating blade and offset arm. In this mode of operation, the regulating blade was capable of responding to any positive reactivity addition and could actuate the regulating rod auto-matic rod run-ins ('10% withdrawn and bottomed) if needed. The ball plunger was
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treated with locktite and was retightened. The regulating blade was exercised over its full travel. The reactor was refueled and returned to normal opera-tion. _
On November 20, with the reactor subtritical during a normal reactor start-up, a short period scram occurred when the detector for the intermediate range monitor channel #3 failed. The detector and -cables for this channel were rc-placed and tested satisfactorily.
On November 28, a manual scram was initiated when the regulating blade was observed to be not responding in either its automatic or manual mode. Subsequent investigation revealed that the regulating blade gear box output shaft had I-8 I
sheared. Due to the recent repetitive regulating blade drive problems, the pull weight of the blade was tested over the full travel length and was found to be correct. The shaft was replaced and the regulating blade operation was tested and found tn be satisf actory. The details of this regulating blade failure were reported in a Licensee Event Report dated December 27, 1988.
Major maintenance items for November included: replacing the solenoid for I valve 546-B (in-pool convective cooling loop); replacing channel 15 detector; replacing channel #3 detector and cables; and replacing the gear box output shaft for the regulating blade drive.
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DECEMBER 1988 The reactor operated continuously in December with the following excep-tions: seven shutdowns for scheduled maintenance and five unscheduled shut-downs.
Twice on December 17 and once on December 18, a nuclear instrument channel
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- 6 (power range monitor) high power rod run-in occurred. In each case, no l actual high power condition was observed on any nuclear instrumentation or related system. The rod run-ins were reset and power was restored within several minutes. After the second of these rod run-ins, the reactor was shut down and the electronic technicians replaced the rod run-in/downscale trip unit -
for channel #6. After the third rod run-in, the reactor was shut down and NI channel #5 and #6 drawers were swapped in an attempt to isolate the problem to the drawer or detector if the problem recurred. --
. Later, on December 18, channel #6 high power scram occurred with, once
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again, no actual high power condition observed. The cables connecting the
! detector for this channel were subsequently discovered to be degraded, and were suspected to be the source of the spurious rod run-ins and scram. The cables I-9 o_
and detector for channel #6 were replaced and rested satisfactorily. The reactor was then returned to operation with no further problems of this type.
On December 31, a spurious nuclear instrument channel #3 (intermediate range monitor) short period scram occurred. The cause for the scram could not be determined. All of the major drawer components, detector cables and con-nectors for this channel were checked, and no obvious malfunctions or discrep-ancies were discovered. The reactor was refueled and returned to normal opera-tion. On the next maintenance day, January 8,1989, further investigation of channel #3 revealed that the insulation for the power lead to channel #3 was brittle and cracked in places. This cable was replaced.
Major maintenance items for December included: changing out the inboard bearing on primary pump 501A; replacing channel #3 detector and cables; re-placing the rod run-in/downscale trip unit in channel #6 drawer; and replacing channel #6 detector and cables. l I JANUARY 1989 The reactor operated continuously in January with the following exceptions:
four shutdowns for scheduled maintenance and one unscheduled shutdown.
t On January 13 a reactor scram was initiated by the failure of relay 2K2.
This relay is located in the yellow leg of the scram system and initiates an evacuation / isolation annunciator alarm and a reactor scram. No other isolation /
evacuation functions (i.e., horns, valves, doors) are initiated by this relay.
The relay was replaced and tested satisfactorily.
Reactor Operations' personnel performed the annual in-house emergency preparedness drill satisfactorily. A reactor operator written examination and operating test was administered by a Nuclear Regulatory Commission examiner l January 18 and 19.
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Major maintenance items for January included: loading eight spent fuel elements into the National Lead cask and transferring it to the beamport floor
.for temporary storage; replacing relay 2K2; and renewing NI channels #5 and #6 power leads.
I FEBRUARY 1989 The reactor operated continuously in February with the following exceptions:
four shutdowns for scheduled maintenance and five unscheduled shutdowns.
On February 2, a nuclear instrument channel #6 Nuclear Instrument Anomaly scram occurred from what was thought to be a malfunction in the channel #6 drawer voltage regulator. The voltage regulator module was replaced and a nuclear instrument check was completed satisfactorily. On two subsequent startup attempts, the reactor scrammed while approaching 10 megawatts 'as the channel #4, I #5, or #6 downscale annunciation alarn cleared.
i There was no safety system scram annunciation or any indication of an actual ~ power increase on either occasion. The specific causes for these scrams were undetermined but it was felt that they had occurred as a result of an annunciator ground loop problem or RF interference problem generated by the annunciator relays.
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On February 10, 1989, a reactor scram occurred coincidently with the channel
- 4, #5, or #6 downscale annunciation alarm. On February 16, another reactor scram occurred coincident with a regulating blade 60% withdrawn annunciation alarm.
Each time no power channel indicated an actual high power and no safety system scram was annunciated. The similarity and timing of these and previous unsched-uled shutdowns again appeared to indicate an annunciator grounding problem, or RF l-
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interference problem generated by the annunciator relays. In order to alleyiate these problems, electronics technicians replaced the channel #4, #5, or #6 downscale annunciator cable, replaced missing connection box covers, and rerouted I-11 l
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some annunciator cables. They have also replaced the cables between the 124 volts DC power supplies which are common to all nuclear instruments and each
- instrument drawer. The 110 volts AC power lead to the nuclear instrument DC power supplies (2PS1, 2PS2) was also replaced. These cables showed signs of degrading due to age.
Major maintenance items for February included: replacing the voltage regu-
.I lator in N1 channel #6; replacing the drawer inoperative /high power trip unit module for N1 channel #6; replacing the channel #4, #5, or #6 downscale annuncia-tor cable; replacing the cables between the 124 volts DC power supply and each NI drawer;. and replacing the 110 volts AC to the nuclear instruments power supplies.
t1 ARCH 1989 The reactor operated continuously in March with the following exceptions:
five shutdowns for scheduled maintenance and one unscheduled shutdown.
On liarch 1, the reactor scrammed due to a momentary site electrical power interruption which was verified by the University Power Plant. The reactor was refueled and returned to normal operation. In a letter dated August 3,1989, the Nuclear Regulatory Commission withdrew the violation based on additional informa-tion provided by 11URR staff at a June 20,_1989 11anagement Meeting.
March 6 through liarch 10, the Nuclear Regulatory Commission performed a team routine safety inspection of the reactor. The findings of this team inspection ,
were reported to liURR in a letter and Notice of Violation dated liay 4,1989. The .
11URR staff submitted responses to this Nuclear Regulatory Comission letter and Notice of Violation in letters dated June 7,1989.
l 11ajor maintenance items for fiarch included: replacing the outer personnel airlock door drive motor and gearbox assembly; repairing the clutch on the outer I personnel airlock door; completing the biennial changeout of control blade offset j l
"D"; and renewing the power cord on the fission product monitor. ;
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I APRIL 198.9_
E The reactor operated continuously in April with the following exceptions:
four shutdowns for scheduled maintenance; and eight unscheduled shutdowns.
On April 3, a channel #5 (power range monitor) high power rod run-in occurred soon af ter placing the reactor in automatic control upon reaching ten megawatts. It was determined that the indicated poder on channel #5 was approx-imately 109% when the reactor was placed in automatic control.
Channel #5 indication subsequently rose to the rod run-in trip set point I- of 114% before the automatic insertion of the regulating blade compensated. The power level indications on the two other power range manitors were within normal l_
operating linits. The rod run-in was reset and the reactor power level set point was adjusted so that indicated power would be lower before again placing the reactor in automatic control. The operators involved in this startup were instructed to pay closer attention to their power indications during this critical' phase of the startup.
On April 7, a reactor scram and isolation was caused by the accidental de-energizing of the Elgar AC line conditioner. While an operator was cleaning up an ink spill, the on/off switch for the line conditioner was inadvertently bumped, de-energizing the unit. The Elgar AC line conditioner supplies power to (among other things) the area radiation monitoring system evacuation and isola-tion relays. These relay contacts opened when the line conditioner was de-I energized and this caused the scram and isolation. The reactor was subsequently The operator involved was instructed to be refueled and returned to operation.
more careful when working around reactor instrumentation.
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On April 18, a channel #4 (wide range monitor) high-power rod run-in occurred. There were no indications of actual high power on any reactor instru-mentation. Af ter determining that all reactor systems and indications appeared I I-13 I
' normal, the rod run-in was reset and a return to power was attempted. Another rod run-in occurred as reactor power passed through 95% and the channel #4, #5,
- 6 downscale annunciator alarm cleared. No other abnormal indications were observed on any instrumentation. Two additional attempts were made to regain power when trying to isolate this problem, both resulting in rod run-ins with no annunciations and again no abnormal indications. The reactor was then shut down to replace a suspected faulty channel #4 downscale alarm / rod run-in dual trip unit. The dual trip unit was replaced and a hot reactor startup wasj attempted.
As reactor power passed through 95%, a rod run-in occurred which appeared to be coincident with the channel #4 downscale alarm clearing. No other annunciations or abnormal indications were observed. The following actions were taken during i the remainder of the day in an attempt to locate and correct the cause of the rod run-ins: the original trip unit in channel #4 drawer was reinstalled and i its trip set points were checked; the moveable contacts for relay 2K35 (channel
- 4, #5, #6 downscale annunciation) were replaced; the channel #4, #5, #6 down-scale annunciation module was replaced; the spare trip actuator amplifier and non-coincident logic unit nodules were installed in the rod ran-in positions; l the channel #4 nuclear instrament detector and cables were replaced; and the inside of the dry well for channel #4 was cleaned.
Electronics technicians confirmed that the primary cause for this series of rod run-ins was an intermittent ground loop created when the detector for I channel #4 became grounded (< 500 k ohms resistance) against its drywell.
Variations in the resistance measurements between the detector and the drywell for channel #4 were found to be detector position specific, indicating that some of the anodizing on the inside of the drywell is worn to the point that bare metal is exposed. Machine Shop personnel have constructed an anodized sleeve I which will be used to surround the detector and reduce the likelihood of this
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type problem.
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I On April 29, a manual rod run-in was initiated when a duty operator noticed fluctuations in primary heat exchanger temperature indication provided l by temperature element 980B. No other temperature anomalies were indicated on any other monitors. An electronics technician isolated the problem to a faulty transmitter for temperature element 980B. The transmitter was replaced, tested, and a compliance check was performed satisfactorily. The reactor was refueled and returned to normal operation.
14ajor maintenance items for April included: replacing the moveable con-tacts for relay 2K35 (channel #4 #5, #6 downscale annunciation); replacing the channel #4, #5, #6 downscale annunciator module; installing the spare trip actuator amplifier and non-coincident logic unit modules in the rod run-in position; replacing the channel #4 detector and cables; replacing the trans-mitter for primary heat exchanger temperature element 980B. During the month, 32 depleted fuel elements were shipped to Idaho National Energy Laboratory, Idaho Falls, Idaho.
14AY 1989 The reactor operated continuously in liay with the following exception:
four scheduled shutdowns for maintenance. There were no unscheduled shutdowns this month.
liajor maintenance items for liay included: performing the annual contain-ment building leak rate test; completing a radioactive waste shipment (irradiated) metal hardware); installing a sample irradiation wedge in position 5A after re-moving the solid graphite wedge; and installing new building ventilation exhaust fan (EF-14); installing fiodification Package #89-2, which jumpers out the blade full in photo cell when the control blade drop timer switch is turned on. This ensures that the control blade drop time is obtained from the photo cell that is set at the blade 20% withdrawn position.
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I JUNE 19,8,9, The reactor operated continuously in June with the following exceptions:
four shutdowns for scheduled maintenance; and eight unscheduled shutdowns.
On June 3, a manual rod run-in was initiated when an operator visually observed that the drive chain for one of two regulating blade rod run-in functions was not attached to its drive sprocket. With the reactor shut down, the chain was reattached to the sprocket wheel and the tension was adjusted. A ,
compliance check to verify the operability of the regulating blade rod run-in functions was completed satisf actorily. A Licensee Event Report detailing the circumstances of this event was sent to the Nuclear Regulatory Commission on June 15,1989.
On June 5, while the reactor was subcritical during a normal startup, a nuclear instrument channel #4 (wide range monitor) high-power rod run-in occurred. No actual high power condition was indicated on any instrumentation.
Electronics technicians attributed the probable cause of the rod run-in to .
detector cable deterioration which caused internit t eat signal spikes. They replacai tha following items for channel #4: the dual trip unit (for the rod run-in and the 95% downscale); the 95% downscale relay K58; the detector and The reactor was then refueled and returned to normal operation._
cables.
On June 9, a nuclear instrument channel #6 (power range monitor) high power rod run-in occurred while an operator was in the process of adjusting the gain j I_ potentiometer to lower indicated power for channel #4. The duty operator failed i i
to place the reactor in manual control prior to beginning this procedure. Con-sequently, a high power condition was created when the regulating blade auto-abtically withdrew to compensate for the mismatch between the channel #4 indication and the power level set. The channel #6 power level indication was I documented as 105% approximately five minutes prior to this event. Channel #6 l I I-16
indicated power increased 9% to reach the 114% high power rod run-in trip.
(This corresponds to a power level of 10.78 MW.)
After determining the cause for the rod run-in, the duty operator reset the rod run-in and the reactor was subsequently returned to normal operation.
The operators involved in this event were instructed to follow proper proce-dures and to assist each other in avoiding errors of this type.
On June 19, a manual rod run-in was initiated during a normal startup when the position indication transmitter for control blade "D" became stuck at the 7.99 inch position. The reactor was subcritical at this blade height and the drive mechanisms for all of the control blades were functioning normal.ly. The 8.00 inch digit on the position indication transmitter was discovered to be mechanically bound. The position indication transmitter was disassembled and lubricated so that its actuators worked freely. A normal startup was then completed with no further pro'>1e is of this type. f ,
On June 21, two nJclear instrument channel #3 (intermediate range monitor) short period scrams occurred. In both cases, the reactor was operating at I 10 MW and no indication of an actual power level change or short period was indicated on any instrumentation. The intermediate range short period rod run-in and scrams are designed to assure protection of fuel e1~ements from <
continuous startup rod withdrawal accident (HSR, Add. 5, Section 5). If an
. actual power transient had occurred at 10 MW, the three power rLnge instrument scram and rod run-in trips would have occurred before a short period trip could occur. The cause of the scrams was subsequently traced to faulty detector cables. The detect er nnd cables for channel #3 were replaced and tested satis-factorily. The reactor was then returned to normal operation.
On June 22, the reactor scracned due to a momentary site electrical power interruption which occurred during a thunderstorm. This was verified by the University Power Plant.
1-17 I
I On June 23, a channel #5 (power range moniter) high power rod run-in occurred shortly after the reactor had undergone an auto shim sequence. (At the regulating blade height position corresponding to 20% of full travel, the con-trol blades are automatically prograraned in until the regulating blade 60%
position is reached.) The regulating blade reached the fully withdrawn position during the last automatically programmed control blade step insertion. The duty operator then shinmed the control blades out to allow the regulating blade to drive in. However, the channel #5 indication increased approximately 9% to the rod run-in set point of 114% before the regulating blade could automatically I _
compensate by driving in. The rod run-in was reset and the proper operation of the regulating blade was observed before returning the reactor to the desired power level.
The timing sequence for the auto-shim circuit was examined and reset so I that the regulating blade would not fully withdraw during this sequence. The operator _ involved in the control blade movement was instructed to observe the power level indications more closely when shimming the control blades.
On June 20, Messrs. A. Bert Davis, Regional Administrator and Ed Greenman, Director Division of Reactor Projects of Nuclear Regulatory Commission Region III met with reactor management to discuss _ items from the March 6-10 team in-spection. The MURR's Director's office also provided Mssrs. Davis and Greenman with an overview of MURR's research, service and educational activities.
Major maintenance items for June included: replacing the dual trip unit,
'~
the 95% downscale relay K58, and the detector and cables for N. I. channel #4; installing new area radiation monitoring system connectors in the containment penetration plate; installing an interlock between the pool isolation valve (V-509) and the pool demineralized pump (P-513B); replacing primary pump 501B; and replacing N. I. channel #3 detector and cables.
(
I-18 1 - - - - - - - - - - _ _
SECTION 11
[
(
l E. CHANGES TO THE STANDARD OPERATING PROCEDURES Revised October 1951 E
1 JULY 1988 THROUGH JUNE 30, 1989 As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following:
STANDARD OPERATING PROCEDURES, 2nd EDITION Effective Date: 5/02/89 (Revisions #1 through #24 to the October 1981 printing have been incorporated.)
I EMERGENCY PROCEDURES _
(dated January.1985 and revised May 13,1988)
I NOTE: New manual printed llay 13,1988)
As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following:
- 1. Revision No. 1, dated 1/11/89
^
- 2. Revision No. 2, dated 5/22/89 NOTE: SEP 1, page 2: Social Security Numbers have been ornitted per request by Nuclear Regulatory Conaission, Al Adams, 9/87.
I The revisions to the Standard Operating Procedures and Emergency Pro-cedures are contained in this section with the part of each page that was _
revised marked on thr. right side of the page by a bracket (3).
I I 11-1 I
i
r I
I STANDARD OPERATING PROCEDURES, 2nd EDITION Effective Date: 5/02/89 (Revisions #1 through 124 to the October 1981 printing have been incorporated.)
4 I
I -
I I .
4-m se I
11-2
I I
I I
STANDARD OPERATING PROCEDURES 2nd Edition Effective Date: 5/02/89 I
(Revisions #1 through #24 to the October 1981 printing have been incorporated.)
I I
I I
I I
UNIVERSITY OF MISSOURI l RESEARCH REACTOR FACILITY I
I I
t .
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1 l
ASSIGNMENT SHEET l
1-UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY I
I STANDARD OPERATING PROCEDURES 2nd EDITION Effective Date: 5/02/89 I (Revisions #1 through #24 to the October 1981 printing have been incorporated.)
I I NUMBER i
1 IS ASSIGNED AS FOLLOWS-I I
i MURR STANDARD OPERATING PROCEDURES I' 2nd Edition Effective Date: 5/02/89
, (Revisions #1 through #24 to the October 1981 printing I' have been incorporated.)
Revision No. Date Filed Revision No. Date Filed Revision No. Date Filed I -
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I I-I I i I
I l I
I I
I I
I TABLE OF CONTENTS. 2nd Edition (Revisions #1 through #24 to the October 1981 printing have been incorporated.)
SECTION NO. PAGE NO.
I ADMINISTRATIVE OPERATING POLICIES . . . . . . . 50P/I-1 I 1.1 1.2 Purpose . . . . . . . . . . . . . . . . . . . .
Scope . . . . . . . . . . . . . . . . . . . . .
50P/I-1 50P/I-1 I.3 Reactor Operating Parameters ......... S0P/I-1 E
E I.4 Administrative Policies . . . . . . . . . . . . SOP /I-2 II REACTOR OPERATING PROCEDURES ......... 50P/II-1 11.1 Routine Reactor Operation . . . . . . . . . . . SOP /II-1 II.2 Fuel Handling Procedure . . . . . . . . . . . . SOP /II-9 11.3 Control Blade Offset Mechanism Removal .... SOP /II-12 11.4 Wa st e Ta nk An al y s i s . . . . . . . . . . . . . . 50P/II-15 III REACTOR CONTROL AND INSTRUMENTATION SYSTEM .. SOP /III-1 111.1 Preparation of Reactor Instrumentation for Operation . . . . . . . . . . . . . . . . . SOP /III-1 I' III.2 Front Panel Checkout of Source Range Monitor Channel 1 . . . . . . . . . . . . . . . 50P/III-2 III.3 Prestartup Check of Intermediate Range Monitor Channels 2 and 3 ........... SOP /III-2 III.4 Prestartup Check of Wide Range Monitor Channel 4 . . . . . . . . . . . . . . . . . . . SOP /III-4 111.5 Check of Power Range Monitor Channels 5 and 6 . 50P/III-5 III.6 Procedure for Physically Adjusting NI Detectors at Power .............. SOP /III-7 III.7 Check of Process Radiation Monitors . . . . . . 50P/III-8 Area Radiation Monitoring System SOP /III-9 I
III.8 .......
IV PRIMARY COOLING SYSTEM ............ 50P/IV-1 IV.1 Startup of Reactor Cooling Loop . . . . . . . . 50P/IV-1 IV.2 Shu'down of Primary System .......... SOP /IV-3 IV.3 Operetion of the Antisiphon System ...... SOP /IV-5 IV.4 Depressurization of Pressurizer . . . . . . . . 50P/IV-6 V P00L COOLING SYSTEM . . . . . . . . . . . . . . SOP /V-1 V.1 Pool Cooling System Startup . . . . . . . . . . 50P/V-1 Pool System Shutdown Procedure V.2 ........ 50P/V-3 l V.3 Partial Pool Filling Procedures (Pool at Refuel Level or Above) . . . . . . . . SOP /V-3 Rev. 5/02/89 App'd l $
s .
I TABLE OF CONTENTS, 2nd Edition (Revisions #1 through #"4 to the October 1981 printing I
have been incorporated.)
l SECTION NO. PAGE NO.
I V.4 Pool Lowering Procedure . . . . . . . . . . . , . SOP /V-4 V.5 Pool Cl eanup System . . . . . . . . . . . . . . SOP /V-5 V,,1 SECONDARY COOLING SYSTEM . . . . . . . . . . . SOP /VI-1 VI.1 Startup of the Secondary System . . . . . . . . SOP /VI-1 VI.2 Procedure for Operation of Bypass Control Valves S-1 and S-2 . . . . . . . . . . . . . . SOP /VI-3 i VI.3 Operation of Cooling Tower Fans . . . . . . . . SOP /VI-5 VI.4 Shutdown of the Secondary System . . . . . . . SOP /VI-S VI.5 Draining and Filling The Secondary System VI.6 Heat Exchanger and Piping . . . . . . . . . . . S0P/VI-7 Secondary Water Treatment Procedures . . . . . SOP /VI-7 l
VII AUXILI ARY SYSTEMS . . . . . . . . . . . . . . . S0P/VII-1 VII.1 Reactor Power Calculator . . . . . . . . . . . SOP /VII-1 VII.2 Ventilation Exhaust System (EF-13/GF-14) . . 50P/VII-2 VII.3 Emergency Power System . . . . . . . . . . . . SOP /VII-3 VII.4 Reactor Demineralized System . . . . . . . . . SOP /VII-4 VII.5 Skimmer System . . . . . . . . . . . . . . . . S0P/VII-15 VII.6 Primary / Pool Drain Collection System . . . . 50P/VII-17 VII.7 Primary and Pool Sample Station . . . . . . . . SOP /VII-19 VII.8 Liquid Waste Disposal System ........ . SOP /VII-20 VII.9 Nitrogen and Valve Operating Air Systems . . . SOP /VII-30 VII.10 Compressed Ai r System . . . . . . . . . . . . . SOP /VII-31 VII.11 Sulphuric Acid System . . . . . . . . . . . . . S0P/VII-35 VIII REACTOR EXPERIMENTS . . . . . . . . . . . . . . SOP /VIII-1 VIII.1 General Requirements . . . . . . . . . . . . . S0P/VIII-1 VIII.2 In-Pool Irradiations . . . . . . . . . . . . . SOP /VIII-5 VIII.3 Pneumatic Tube (P-tube) System Irradiations . . SOP /VIII-8 VIII.4 Beamport Experiments . . . . . . . . . . . . . SOP /VIII-19 VIII.5 Handling and Release of Irradiated Samples . . S0P/VIII-38 VIII.6 Response Procedures for the Nuclepore Irradiation Facility . . . . . . . . . . . . . S0P/VIII-38 VIII.7 Thermal Column Door Operations . . . . . . . . SOP /VIII-40 ii Rev. 5/02/89 App'd tM
TABLE OF CONTENTS, 2nd Edition (Revisions #1 through #24 to the October 1981 printing have been incorporated.)-
I SECTION NO. PAGE NO.
REACTOR EMERGENCY PROCEDURES: j Table of Contents . . . . . . . . . . . . . . . . . . . . . . REP-0-1 REP-0 Introduction .................... REP-0-2 +
REP-1 Failure to Scram or Rod Run-In. . . . . . . . . . . . REP-1-1 REP-2 Reactor Scram from Causes Other Than Loss of Flow or Pressure . . . . . . . . . . . . . . . . . . . . . REP-2-1 .,
REP-3 Reactor Scram from Loss of Primary System Pressure g or now ...................... REP-3-1 REP-4 High Radiation ................... REP-4-1 REP-5 Nuclear Instrument Failure ............. REP-5-1 9 i
REP Failure of the Area Radiation Monitoring System (ARMS) . . . . . . . . . . . . . . . . . . . . REP-6-1 REP-7 Loss of Communications Between Reactor Control Room and Experimenters ............... RED-7-1 I REP-8 Control Rod Drive Failure ............. REP-8-1 REP-9-1;-2;-3 REP Electrical Anomalities ...............
REP-10 Failure of Experimental Apparatus . . . . . . . . . . REP-10-1 REP-11 Low Fire Main Pressure ............... REP-11-1 REP-12 Loss of Service Water to Facility . . . . . . . . . . REP-12-1 REP-13 Loss of Secondary Flow ............... REP-13-1;-2 REP-14 Loss of Pool Flow During Reactor Operation ..... REP-14-1 REP-15 Loss of Pool Water Level During Reactor Operation . . REP-15-1;-2;-3 REP-16 Valves 507A and 5078 Fail to Close ......... REP-16-1 I REP-17 Pressurizer Valves Fail to Operate ......... REP-17-1 REP-18 Both Antisiphon Valves (543A and 5438) Fail to Open . REP-18-1 REP-19 Failure of Emergency Core Cooling Valves (546 A/B). . REP-19-1 REP-20 High Activity Levels in the Primary Cooling . . . . .
System (FPM) .................... REP-20-1;-2 REP-21 High Stack Monitor Indications ........... REP-21-1;-2;-3 i REP-22 Bomb or Other Overt Threats . . . . . . . . . . . . . REP-22-1 I iii Rev. 5/02/89 App'd llM I l
TABLE OF CONTENTS, 2nd Edition i (Revisions #1 through #24 to the October 1981 printing have bee: incorporated.)
SECTION N0. PAGE NO.
APPENDIX A:
SOP /A-1 Reactor Startup Checksheet-Full Power Operation . . SOP /A-la;-lb SOP /A-2 Deviation from Standard Operating Procedure . . . . 50P/A-2a;-2b SOP /A-3 Reactor Short-Form Pre-Critical Checksheet .... SOP /A-3a;-3b SOP /A-4 Reactor Shutdown Checksheet . . . . . . ...... S0P/A-4a;-4b SOP /A-5 Nuclear Data / . . . . . . . . . . . . . . . . . . . SOP /A-Sa;-5b Process Data ................... SOP /A-Sc;-5d S0P/A-6 Startup Nuclear Data ............... SOP /A-6a;-6b SOP /A-7 Pneumatic Tube Irradiations . . . . . . . . . . . . S0P/A-7a;-7b SOP /A-8 Reactor Routine Patrol .............. S0P/A-Ba;-8b
-8c;-8d SOP /A-9 Unscheduled Reductions in Power Report No. .. 50P/A-9a;-9b SOP /A-10 Radiation Work Permit . . . . . . ..... ... S0P/A-10a-10b SOP /A-11 Waste Tank Sample Report ............. 50P/A-11a;-11b SOP /A-12 Primary System Normal Operating Valve Lineup Checksheet . . . . . ............ SOP /A-12a;-12b
-12c;-12d SOP /A-13 Secondary Water Activity Analysis . . . . . . . . . 50P/A-13a;-13b S0P/A-14 Pool System Valve Lineup Checksheet . . . . . . . . 50P/A-14a;-14b
-14c;-14d SOP /A-15 MURR Pool Water Analysis ............. SOP /A. Sa;-15b SOP /A-16 D. I. 200 Series Resin Log For Bed _...... SOP /A-16a;-16b S0P/A-17 TAG - DO NOT OPERATE ............... SOP /A-17a;-17b S0P/A-18 D. I. Water Makeup Log (Fill in only if sending j D. I. water.) . . . . . . . . . . . . . . . . . . . 50P/A-18a;-18b SOP /A-19 MURR Operator Active Status Log . . . . . . . . . . S0P/A-19a;-19b I l
l APPENDIX B:
SOP /B-1 Toxic Materials With Restricted Use in The Containment Building ............. SOP /B-la;-lb l
l Rev. 5/02/89 App'd M I
L 3 LIST OF EFFECTIVE PAGES, 2nd Edition (Revisions #1 through #24 to the October 1981 printing have.been incorporated.)
Page Number Date Revised Page Number Date Revised Title Page 5/02/89 ] SOP /II-14 Reset 5/02/89 ]
SOP /II-15 5/02/89 ]
Ass'ignnent Sheet 5/02/89 ] SOP /II-16 5/02/89 ]
Revision-No. & Date Page 5/02/89 ] S0P/III-1 5/02/89 ]
SOP /III-2 5/02/89 ] q I Table iof Contents: 5/02/89 ] SOP /III-3 10/81 ii 5/02/89 ] S0P/III-4 10/81
> iii 5/02/89 ] SOP /III-5 10/81 iv 5/02/89 ] SOP /III-6 7/30/85
. List of Effective Pages: SOP /III-7 5/02/89 ]
v 5/02/89 ] SOP /III-8 5/02/89 ]
] ]
vi 5/02/89 SOP /III-9 5/02/89 -
vii 5/02/89 ] SOP /III-10 5/02/89 ] )
viii 7/03/85 SOP /III-11 5/02/89 ] -
SOP /III-12 10/81 .
ISOP/I-1 5/02/89 ]
SOP /I-2 5/02/89 ] S0P/IV-1 10/81 5/02/89 ] SOP /IV-2 5/02/89 ]
ISOP/I-3 SOP /I-4 5/02/89 ] SOP /IV-3 10/81 SOP /I-5 5/02/89 ] SOP /IV-4 5/02/89 ]
S0P/I-6 5/02/89 ] SOP /IV-5 10/81 5/02/89 ] SOP /IV-6 5/02/89 ] '
ISOP/I-7 S0P/I-8 5/02/89 ]
S0P/I-9 5/02/89 ] SOP /V-1 5/02/89 ]
E 50P/I-10 5/02/89 ] SOP /V-2 5/02/89 ]
= S0P/I-11 5/02/89 ] S0P/V-3 5/02/89 ]
SOP /I-12 5/02/89 ] S0P/V-4 5/02/89 ]
SOP /I-13 5/02/89 ] SOP /V-5 5/02/89 ]
SOP /I-14 5/02/89 ] SOP /V-6 5/02/89 ]
S0P/I-15 5/02/89 ]
SOP /I-16 5/02/89 ] S0P/VI-1 5/02/89 ]
SOP /I-17 5/02/89 ] SOP /VI-2 5/02/89 ]
50P/I-18 5/02/89 ] SOP /VI-3 5/02/89 ]
SOP /I-19 5/02/89 ] SOP /VI- 4 5/02/89 ] '
SOP /I-20 5/02/89 ] S0P/VI-5 5/02/89 ]
SOP /VI-6 5/02/89 ]
SOP /II-1 5/02/89 ] SOP /VI-7 5/02/89 ]
SOP /II-2 5/02/89 ] S0P/VI-8 5/02/89 ] ~
SOP /II-3 5/02/89 ] S0P/VI-9 5/02/89 ]
S0P/II-4 5/02/89 ] S0P/VI-10 5/02/89 ]
SOP /II-5 10/81 SOP /II-6 5/02/89 ] SOP /VII-1 10/81 SOP /II-7 12/16/86 SOP /VII-2 3/12/86 SOP /II-8 5/02/89 ] SOP /VII-3 5/02/89 ]
SOP /II-9 5/02/89 ] SOP /VII-4 5/02/89 ]
SOP /II-10 5/02/89 ] SOP /VII-5 5/02/89 ]
$9P/II-11 5/02/89 ] S0P/VII-6 5/02/89 ] .<
SOP /II-12 5/02/89 ] SOP /VII-7 5/02/89 ]
50P/II-13 5/02/89 ] .
v Rev. 5/02/89 App'd b -
LIST OF EFFECTIVE PAGES, 2nd Edition l (Revisions #1 through #24 to the October 1981 printing l have been incorporated.)
Page Hunber Date Revised Page Number Date Revised l
l S0P/VII-8 5/02/89 ] SOP /VIII-20 Reset 5/02/89 ]
SOP /VII-9 5/02/89 ] SOP /VIII-21 5/02/89 ]
S0P/VII-10 5/02/89 ] SOP /VIII-22 5/02/89 ]
SOP /VII-11 5/02/89 ] SOP /VIII-23 5/02/89 ]
SOP /VII-12 5/02/89 ] SOP /VIII-24 5/02/89 ]
SOP /VII-13 5/02/89 ] SOP /VIII-25 5/02/89 ]
SOP /VII-14 5/02/89 ] SOP /VIII-26 5/02/89 )
SOP /VII-15 Reset 5/02/89 ] SOP /VIII-27 5/02/89 ]
L SOP /VII-16 5/02/89 ] SOP /VIII-28 5/02/89 ]
S0P/VII-17 Reset 5/02/89 ] SOP /VIII-29 5/02/89 ]
SOP /VII-18 5/02/89 ] S0P/VIII-30 5/02/89 ]
SOP /VII-19 5/02/89 ] S0P/VIII-31 5/02/89 ]
SOP /VII-20 5/02/89 ] SOP /VIII-32~ 5/02/89 ]
S0P/VII-21 5/02/89 ] SOP /VIII-33 5/02/89 ]
SOP /VII-22 5/02/89 ] SOP /VIII-34 5/02/89 ]
S0P/VII-23 5/02/89 ] SOP /VIII-35 5/02/89 ]
SOP /VII-24 5/02/89 ] S0P/VIII-36 5/02/89 ]
SOP /VII-25 5/02/89 ] SOP /VIII-37 5/02/89 ]
SOP /VII-26 5/02/89 ] SOP /VIII-38 5/02/89 ]
SOP /VII-27 5/02/89 ] SOP /VIII-39 Reset 5/02/89 ]
SOP /VII-28 5/02/89 ] S0P/VIII-40 Ruset 5/02/89 ]
SOP /VII-29 Reset 5/02/89 ] SOP /VIII-41 5/02/89 ]
SOP /VII-30 5/02/89 ] SOP /VIII-42 Reset 5/02/89 ]
SOP /VII-31 5/02/89 ']
S0P/VII-32 5/02/89 ] REACTOR EMERGENCY PROCEDURES S0P/VII-33 5/02/89 ]
S0P/VII-34 5/02/89 ] REP-0-1 (Table of C) 5/02/89 ]
SOP /VII-35 5/02/89 ]
SOP /VII-36 5/02/89 ] REP-0-2 7/30/85 SOP /VIII-1 10/81 REP-1-1 Orig. 7/03/85 SOP /VIII-2 5/02/89 ]
SOP /VIII-3 5/02/89 ] REP-2-1 Orig. 7/03/85 SOP /VIII-4 5/02/89 ]
SOP /VIII-5 5/02/89 ] REP-3-1 Orig. 7/03/85 SOP /VIII-6 5/02/89 ]
SOP /VIII-7 5/02/89 ] REP-4-1 Orig. 7/03/85 50P/VIII-8 Reset 5/02/89 ]
SOP /VIII-9 5/02/89 ] REP-5-1 Orig. 7/03/85 SOP /VIII-10 5/02/89 ]
SOP /VIII-11 5/02/89 ] REP-6-1 5/02/89 ]
SOP /VIII-12 5/02/89 ]
SOP /VIII-13 5/02/89 ] REP-7-1 Orig. 7/03/85 S0P/VIII-14 Reset 5/02/89 ]
SOP /VIII-15 Reset 5/02/89 ] REP-8-1 Orig. 7/03/85 S0P/VIII-16 5/02/89 ]
' SOP /VIII-17 Reset 5/02/89 ] REP-9-1 Orig. 7/03/85 S0P/VIII-18 Reset 5/02/89 ] REP-9-2 5/02/89 ]
SOP /VIII-19 Reset 5/02/89 ] REP-9-3 Orig. 7/03/85 Rev. 5/02/89 App'd M
LIST OF EFFECTIVE PAGES, 2nd Edition (Revisions #1 through #24 to the October 1981 printing have been incorporated.)
ag Nunber Pag,e Date Revise _d_ Page Number Date Revised
' REPt 10-1 Orig. 7/03/85 S0P/A-6a 3/09/83 50P/A-6b 5/02/89 3 I REP-11-1 Orig. 7/03/85 l SOP /A-7a 9/19/83 REP-12-1 5/02/89 ] S0P/A-7b 6/80 REP-13-1 5/02/89 ] SOP /A-8a 5/02/89 ]
REP-13-2 Orig. 7/03/85 SOP /A-8b 5/02/89 ]
F0P/A-8c 5/02/89 ]
REP-14-1 Orig. 7/03/85 S0P/A-8d 5/02/89 ]
REP-15-1 5/02/89 ] SOP /A-9a 5/02/89 ]
REP-15-2 Orig. 7/03/85 SOP /A-9b 6/80 REP-15-3 Orig. 7/03/85 SOP /A-10a 10/08/86 REP-16-1 Orig. 7/03/85 50P/A-10b 10/08/86 REP-17-1 Orig. 7/03/85 S0P/A-11a 10/08/86 SOP /A-11b 12/15/82 REP-18-1 Orig. 7/03/85 SOP /A-12a 5/02/89 ]
REP-19-1 Orig. 7/03/85 SOP /A-12b Reset 5/02/89 ]
S0P/A-12c Reset 5/02/89 ]
REP-20-1 5/02/89 ] S0P/A-12d Reset 5/02/89 ]
REP-20-2 5/02/89 ]
SOP /A-13a 5/02/89 ] --
REP-21-1 Orig. 7/03/85 SOP /A-135 Reset 5/02/89 ]
REP-21-2 5/02/89 ]
REP-21-? Orig. 7/03/85 SOP /A-14a 5/02/89 ]
S0P/A-14b Reset 5/02/89 )
REP-22-1 Orig. 7/03/85 S0P/A-14c Reset 5/02/89 ]
S0P/A-14d Reset 5/02/89 ]
APPENDIX A
~
SOP /A-15a 5/02/89 ]
SOP /A-la 5/02/89 ] S0P/A-15b Reset 5/02/89 ]
SOP /A-lb- 5/02/89 ]
SOP /A-16a Reset 5/02/89 ]
SOP /A-2a 5/02/89 ] SOP /A-16b Reset 5/02/89 ]
SOP /A-2b 5/02/89 ]
SOP /A-17a Reset 5/02/89 ]
SOP /A-3a 5/02/89 ] S0P/A-17b Reset 5/02/89 ]
S0P/A-3b 6/80 SOP /A-18a Reset 5/02/89 ]
SOP /A-4a 5/02/89 ] SOP /A-18b Reset 5/02/89 ]
SOP /A-4b 5/02/89 ]
SOP /A-19a 5/02/89 ]
SOP /A-Sa 5/74 S0P/A-19b 5/02/89 ]
S0P/A-5b 7/30/85 SOP /A-Sc 4/79 APPENDIX B
~~
S0P/A-5d 6/80 SOP /B-la 5/02/89 ]
S0P/B-lb Reset 5/02/89 ]
Rev. 5/02/89 , App'd M ..
~~~ - - - - - - - - - - - - - _ _ - - _ - - - _ - - - , - - - _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
THIS PAGE INTENTIONALLY LEFT BLANK
.{i Rev. 7/03/85 App'd { M
I SECTION I ADMINISTRATIVE OPERATING POLICIES I.1 Purpose To establish methods of operation for the reactor and associated systems which assure safety and performance within the technical specifications set forth for the University of Missouri Research Reactor.
I.2 Scope I These procedures are not to be construed to constitute a part of 4 the technical specifications. In event of any discrepancy between I the information given herein and the technical specifications, limits set forth in the technical specifications apply. Changes I to these procedures and to any other special operating or mainte-nance procedures which have safety significance must be reviewed by the Reactor Procedures Review Subcommittee (RPRS). Changes which are editorial or have no safety significance may be made by l the Reactor Manager, Reactor Operations Engineer or the Shift Supervisor but must be documented and subsequently reviewed by the RPRS. The documentation will be done by filling out a S0P ]
Deviation Form (see Appendix A) to petition a S0P change or to ]
explain the deviation. ]
I 1.3 Reactor Operating Parameters I The reactor will be operated under conditions and limitations as set forth in the technical specifications, Appendix A to License I R-103.
I Rev. 5/02/89 App'd W M \ S0P/I-1
l I
I.4 Administrative Policies I.4.1 Standing Orders New procedures prior to becoming part of these Stending Operating Procedures, procedures to be in effect for a short period, and ,
and special instructions relating to operation of the reactor, will be issued as Standing Orders. All effective Standing Orders, as well as a listing of current orders, will be main-tained in a log in the reactor control room. Standing Orders l
that are no longer applicable or that are incorporated into i the Standard Operating Procedures will be cancelled and removed from the log. All Standing Orders will be approved by signat 'e of the Reactor Manager or his authorized delegate.
I.4.2 General Operating Policies ,
A. Safety Safe operation of the reactor will take precedence over other considerations.
B. Supervisory Authority The importance of one coordinator for all reactor activities is recognized for safety and effective control of operation.
The Reactor Manager will have complete operating authority over all activities related to reactor operatior.
The Shift Supervisor is the Reactor Manager's delegated ]
representative on shift and is given the authority to direct ] ;
the activities (both licensed and unlicensed) related to ]
reactor operation during his duty shift. ]
Whenever the Shift Supervisor is absent, a Senior Opera- ]
tor shall assume the lead Senior Operator position. The lead ]
Senior Operator is delegated the Shift Supervisor's authority ]
and responsibility for shift activities during the Shift ]
Supervisor's absence.
Any S0P reference to Shift Supervisor apolies to the
]
]
l lead Senior Operator when the Shift Supervisor is absent from ]
his duty shift. ] l Rev. 5/02/89 App'd M SOP /I-2 ]
I
m-1, C. Operating Crews The minimum number of reactor operators for reactor opera-tion will be two licensed persons. One of these will be I licensed as a Senior Operator. There will be one licensed operator in the control room at all times whenever the reactor is not considered secured, as defined in Part 1.1 I of the Technical Specifications. Exception: It is not necessary to have the control room manned during refueling.
These activities may be directed from the reactor bridge.
D. Console Log A log will be maintained in the control room by the reactor ]
I operator providing a detailed diary of reactor operation.
Corrections to console log, Nuclear and Process Data
]
]
E.
and Routine Patrol Sheets ]
Any corrections to a log entry or data sheet will be done by ]
l a single
- through the incorrect entry, plus the initials ]
of the person .naking the change. If the correction is made at a later date, the person making the correction will
' initial and. date the change.
F. Changing Reactor Reactivity ]
Operations affecting changes in core reactivity, other than normal steady state power control, i.e. refueling, startup, I G.
etc., will be directly supervised by a Senior Operator.
Malfunction of Reactor Systems While at Power ]
Any malfunction or abnormal operation of a control or reactor system shall be immediately brought to the attention of the ]
Shift Supervisor. The decision as to whether to continue operation of the reactor depends upon the severity of the malfunction. It remains with the Shift Supervisor as to what immediate action needs be taken. However, the duty operator M authorized, in the absence of the Shift Supervisor from the control room, to place the reactor in a safe shutdown mode if he deems it necessary. It is important that the I reactor systems, while the reactor is critical, not be experimented with, or reactor control systems tested, unless Rev. 5/02/89 App'd @pn(V\ SOP /I-3 ]
I permission to do co is explicitly granted by either the Reactor Manager or his designated representative.
H. Maintenance Performed on Reactor Systems ]
All maintenance on reactor and license related systems and equipment will be reviewed by the Shift Supervisor or Acting Shift Supervisor to ensure operability of these systems prior to reactor operation.
I. Maintaining Active Operator Status ],
Actively performing the functions of an operator or senior ]
operator means that an individual has a position on the shift ] ,
crey!.that requires the individual to be licensed as defined ]
in 10 CFR 55, and that the individual carries out and is ]
responsible for the duties covered by that position. ]
If an Operator has not performed licensed duties a minimum of four hours on shift per calendar quarter, before ]
resumption of licensed activities, the Reactor Manager shall ]
certify that the qualifications and status of the Operator ]
are current and valid, and that the operator has completed a ]
minimum of six (6) hours of shift functions under the ]
direction of a Senior Operator before returning to active ]
status. ]
E J. Reactor Operating Parameters ] E The reactor shall be operated in strict accordance with the Reactor License R-103 and the operating limits in Tables III and IV.
I.4.3 Startup A. Startup Following a Scram The reactor will not be started up following a scram until the cause of the scram has been determined and safe cor-rective action taken. If, after thorough investigation, the cause of the unscheduled reduction in power cannot be determined and all systems are founo to be normal, the j reactor may be started up with the approval of the Reactor l Manager or his authorized delegate.
Rev. 5/02/89 App'd ldQW\ S0P/I-4 ] j
]
I
r B. Occupancy of the Reactor During reactor startup or transient operation, occupancy of the control room and containment building will be limited to the reactor staff, experimenters, and those observers as
' approved by the Reactor Manager or Shift Supervisor. ]
C. Operator Change During Transients 2
Control of the reactor will not be transferred from one operator to another daring power transient operations. ]
f '
Con:rol of the reactor may be transferred at any point ]
L up to and including 2" below estimated critical position ]
during normal reactor startups, if the Senior Operator ] ;
directing the startup deems it necessary. ]
D. Control Blade Operation j
- 1. The control blades shall not be moved in gang control after the reactor is critical except to reduce power (II.1.4.C.2), shutdown the reactor, as part of the ] !
automatic shimming operation, or during a hot startup. ]
1 not be h ra n i 1 n si ith e reg g blade.
E. Hot startup i A startup within two hours of any shutdown, in which restart capability is in doubt, shall be called a hot startup. A hot ,
startup shall only be made by the Shift Supervisor, Senior l Reactor Operator, or a licensed Reactor Operator under the direct and close supervision of a Senior Reactor Operator.
The approach to critical may be made entirely in gang control of the control rod drives.
F. Startup Checksheet
- 1. A Full Power Startup Checksheet will be completed before ]
nuclear operation of the .eactor. The completed check-sheets will be apprrved in writing by the Shift Super-visor before withdrawing the control rods for the ]
startup. A short form Startup Checksheet is provided ]
and may be used tcc a reactor system startup checkout ]
if the following conoMio,1s are satisfied:
Rev. 5/02/89 App'd NM SOP /I-5 ]
l I
L
- a. The systems and instrumentation not covered by the ]
short form Startup Checksheet have been in ]
continuous operation with no anomalies since the ]
completior. of the last Full Power Startup Checksheet ]
and the routine systems check has revealed no abnor-malities.
- b. A Full Power Startup Checksheet has been e mpleted ]
within eight hours prior to the time a short form .
checksheet is to be used, ,or,the reactor has been operating at some time within the previous eight hours, and a Shutdown Checksheet has not been completed during this period.
- 2. A Startup Checksheet is not required for a return to power within a period of two hours following a shutdown from full power, providing the status of any system covered by the Full Power or short form Startup Check- ]
sheets has not changed since the last power operation, or if the Shift Supervisor determines that no system has been adversely affected by the cause of the shut- ]
down.
G. Estimated Critical Position (ECP)
- 1. The Shift Supervisor shall assure that he has a reliable estimated critical position, established by calculation or experience, and record it on the Startup Checksheet prior to each startup. .l
- 2. The estimated critical position shall be either furnished by or approved by the Reactor Physicist on any startup following a shutdown in which fuel handling has taken place. The limits as specified in Table Il shall apply !
to ECP's furnished in this event.
I I
Rev. 5/02/89 App'd NOAM SOP /I-6 ]
I
- 3. The Shift Supervisor may call upon the Reactor Physicist f
at any time to establish a predicted critical position.
The responsibility of assuring that operations has a reliable ECP shall rest with the Reactor Physicist.
- 4. The MURR Estimated Critical Position Procedure (provided ]
by the Reactor Physicist) may be used at the discretion ]
of the Shift Supervisor for cores with previous power ]
5 history and no fuel handling since previous shutdown. ]
However, if the estimate of ECP based upon past history ]
is off by more than that shown in Table I, the control rods will be driven in and the ECP calculated.
- 5. If the reactor is not critical at ECP as calculated by the Reactor Physicist or by the procedure (plus the values shown in Table I or after fuel handling as in Table II),
the reactor will be shutdown, and if not present, the Reactor Physicist will be notified. The reactor is not ]
to be restarted without approval of the Reactor Manager or Reactor Operations Engineer unless the discrepancy between ECP and actual critical position has been unquestionably resolved.
Table I ECP Acceptable Limi_t_s, 11"-16" 0.75" 16"-22" 1.25" 22"-26" 2.50" Table II ECP Acceptable Limits 11"-16" 0.40" 16"-22" 0.70" 22"-26" 1.25" Rev. 5/02/89 App'd (IATW\ 50P/I-7 ]
~
4 s
H .- . Instrumentation e - Minimum Nuclear Instrumentation for startups shall .be one source channel, two intermediate range channels each with period' trips, two power channels. each with flux trips, 'and ]'
one wide range . channel. with high flux trips. .].
. I'. Use of the Public Address System Immediately prior to actual movement of the control rods,-
an announcement will be made over the public' address sys
~
~ tem that.a reactor:startup has been commenced. A'second.
announcement ~ will be made when the des. ired. power level is1 obtained. If'during the startup the determination is'made that power will be . held constant at any level for a period of greater than five minutes an additional announcement-be made to inform building personnel.
LJ. Health Physics Monitoring of Reactor Experiments During a Reactor Startup
- When a. change is made to a.beamport or other reactor b experiment which could lead to significant alterations in area radiation levels as reactor power is increased,.a Health Physics Technician will be assigned to monitor that' ]
experiment' during the startup. Direct communications will '].
be maintained between the Control Room and the Health Physics Technician. The Control Room will inform the Health
- Physics Technician at the following power levels:
- 1. During a Normal Reactor Startup
- a. When the reactor reaches criticality.
- b. When reactor power reaches 50 KWs.
! c. When reactor power reaches 5 MWs (2.5 MWs if L operating in Mode II).
- 2. During a Reactor Hot Startup
- a. When the reactor reaches criticality.
- c. When reactor power reaches 10 MWs.
i Rev. 5/02/89 App'd Npd S0P/I-8 3 O - - - - - -- . _ - _ - _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
If direct communications are lost or if one of the above reports is not acknowledged, reactor power will be main-tained at a steady level until the problem is corrected.
The Health Physics Technician will make his final report to the Control Room af.er a complete survey is conducted at the desired power level.
I.4.4 Normal Operation A. Normal power level will be 9.90 to 10.00 MW as indicated by the total power meter.
B. The control room shall be occupied by at least one licensed ]
operator during steady state operation of the reactor and a ]
second licensed operator at a facility location where com- ]
munication with the control room can be maintained.
C. Prior to assuming control of the reactor, the oncoming oper-ator will read the control room log book and shall be briefed on current operation.
D. During shift operation, the Shift Supervisor for the new shift will review the log book and be briefed on current operations by the crew he is to relieve. Upon completion of the log book review, the Shift Supervisor will note the same
'n the log book.
E. A complete set of Nuclear data will be taken once an hour during steady state operation.
F. A complete set of Process data will be taken every two (2) hours during steady state operation.
G. During routine operation, a routine patrol of the facility will be made every four (4) hours according to an approved Routine Patrol Checksheet.
H. Normally, the calorimetric determination of the power level can be read directly from the digital readout and entered in the Nuclear Process Data. The cause of any difference between the primary and secondary calorimetric calculations which exceeds 5% (0.5 MW) during steady state full power operation should be determined. The primary power Rev. 5/02/89 App'd V0hTA S0P/I-9 ]
p
~,' ,-
y , calculation will'normally'be used to establish the 10 MW.
power levei, however, the nominal steady stat'e power levelf
.shall1 not exceed 10 MW. The reactor'shall not be operated at a; power level which causes the steady state secondary '
h calorimetric to . exceed 10.5 MW 'unless it is confirmed that.
the secondary calorimetric is in error or 'out of commission.
n The primary system. DI: flow bypasses- the . core and yet it ,
, flows. through the primary' flow orifice. Therefore, the primary flow'as read onJthe recorder should be decreased by .
the primary DI flow before the value is used in calculating. l the power level.- The recorder values ~ should be logged on
~
the . log sheets without correction.
~I. Steady state reactor powers of .1 MW and greater will be determined-by the method stated above. The power indicated by Channels .4, 5, and 6 shall be maintained greater than.
100% during steady state full power operation. Channels ~4, 5, and 6 are adjusted by proper positioning of the; drawer amplifier feedback potentiometers. After adjustment of a potentiometer, the change in indicated power shall be' logged in the console log and the new pot setting logged on the Startup Nuclear Data Sheet. The Shift Superyisor's approval must be obtained before adjustment of any Power Range Monitor. Adjustments shall ~be made after a determination ]
of the power level by heat balance with -one exception. ]
During or shortly after a normal reactor startup, and at the .]
Shift Supervisor's discretion, the pot adjustments may be ]
made when an accurate heat balance is not yet possible due ]
to changing temperatures. In all cases, the Shift Super- ]
visor must ensure that the pots are adjusted only in the. ]
conservative direction, that is, in a direction that over -]
estimates actual power. ]-
J. Minimum nuclear' instrumentation for normal operation shall be two (2) intermediate range channels with period trip, two (2) power range channels each with high flux trips and one (1) wide range channel with high flux trip.
Rev. 5/02/89 App'd (MM SOP /I-10 ]
r.p
a, K. During reactor operation the control room shall be occupied only by persons authorized by the Reactor Manager or Shift l l
Supervisor.
I.4.5 Shutdown A. Shutdown operations will be accomplished under conditions designed to assure safety of the reactor and personnel.
B. Shutdown of the reactor will be in accordance with approved j procedures.
C. Conditions causing automatic shutdown of the reactor will be investigated as to cause, and corrective action taken prior to restarting the reactor.
D. Unscheduled shutdown sheets will be filled out for all unplanned rod run-ins and scrams that occurred while at power or after all drive full in lights have cleared when pulling rods to take the reactor critical.
E. Entry into controlled access high radiation areas following ]
reactor shutdown shall be preceded by a radiation survey or as per Health Physics 50P (HP-2).
F. The Shift Supervisor shall have a shutdown checksheet performed if the control room will be unattended for an extended period of time.
G. An entry in the console log book that the reactor has been shut down after an operating or testing period shall be made ]
by the reactor operator assigned to the console.
I.4.6 Experiments ;
A. The Reactor Manager will have operating authority over all experiments performed within the reactor containment or which may affect reactor operations.
B. All experimental programs will be evaluated by the reactor operating organization and by the Reactor Manager.
C. Experimenters are required to inform the reactor control room of any activity which may affect reactor operation.
Rev. 5/0.2/89 App'd @ M SOP /I-11 ]
o.,
m.
i D. All experimenters will be required.to complete an indoctri-nation training course on the.. relationship between his l
. experiment and.. reactor operations, emergency procedures, and l
radiation safety. .
I.1 A11: reactor. users shall complete a Reactor Utilization
. Request form. This request must be' reviewed and approved by the Reactor Manager. .
F. If an experiment. appears to involve new or unevaluated hazards, a review of the proposed experiment by the Reactor Advisory Committee may'be requested b'y the Reactor Manager.
G. The Reactor Manager may require, as deemed-necessary for safe operation, that experimental data or operating instructions.
be on file with the reactor operations organization'.
H. ' All changes in beamport experiments, and intentional flood-ing or draining of the beam tubes to be performed with the-reactor at power will be-done only after written approval is initially obtained from the Reactor Manager and after a pro-cedure for so doing has been established. Whenever practi-cal, beamports shall be flood'ed or drained only after the reactor has been shutdown for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I. The insertion and- removal of experiments in the center test hole position will be done with the reactor shutdown.
I.4.7 Radiation Work Permit A Radiation Work Permit will be completed by the Job Supervisor and Health Physics prior to conducting any work which in the opinion of the Shift Supervisor or the Health Physics Group ]
involves significant potential for exposure of personnel to radiation or the spreading or release of airborne or surface contamination.
-A copy of this form is included in the Appendix of the S0P.
The form is used as follows:
Rev. c;f np f po App'd NMW SOP /I-12 ]
A. The top portion of the RWP will be prepared by the Job ]
L Supervisor and Health Physics. The time and date spaces ]
should contain the supervisor's estimate of the duration ]
of the job (0800-2400 September 2, 1988; 0000-2400 ]
September 10-12,1988,etc.). The Job Supervisor should ]
be as specific as possible in describing the job. This will aid Health Physics in determining the protective measures necessary.
B. Health Physics will assign a number to the RWP and conduct ]
the necessary surveys and determine the protective measures ]
necessary for the job. Health Physics will complete the ]
remainder of the RWP indicating the survey results and the ]
protective measures required. Health Physics will then ]
sign and date the RWP, and obtain approval signature from ]
the Job Supervisor and information signature from the Shift ]
Supervisor, if appropriate. ]
C. The Job Supervisor will provide Health Physics with the names ]
of personnel expected to work under the RWP prior to the ]
start of the job. Each person performing work under the RWP ]
shall be informed of the required radiation controls and ]
shall acknowledge being informed by signing on their ]
designated signature line. Health Physics will have avail- ]
able the approved RWP at the job site for ready reference by ]
the personnel doing the work. ]
D. When the job has been completed and the job site has been ]
cleaned up and decontaminated, the Job Supervisor will deliver ]
the RWP to Health Physics. Health Physics will verify that ]
the job site is clean and decontaminated, and will record ]
estimated dose for each person involved. Health Physics will ]
terminate the RWP and maintain it in an RWP file. Any person ]
who signed approval or any supervisor can terminate the RWP ]
by signing the termination block. Health Physics must be ]
notified if the RWP is terminated by someone other than a ]
member of the Health Physics Group. ]
Rev. 5/02/89 App'd dM SOP /I-13 ]
I.4.8 Radiation Safety The Shift Supervisor is directly responsible for the overall safety of personnel on his shift and indirectly responsible for all personnel whose safety may be affected by activities con-ducted under his supervision. Radiation safety is a very im-portant part of this responsibility. It should not be construed that surveys, monitoring, or other measurements to check for contamination or radiation are to be made by operations person- i nel, but rather that the Shift Supervisor is responsible to insure that through coordination with the Health Physics person-nel, adequate protection is provided for evolutions conducted during his shift.
I.4.9 Physical Protection of Special Nuclear Materials In accordance with 10 CFR 73, special requirements must be met in safeguarding Special Nuclear Material. The safeguards provided and the procedures applicable to maintaining the security of Special Nuclear Materials are contained in the facility Security Plan and Security Procedures.
1.4.10 Equipment Tag Out Procedure I.4.10.1 Purpose The purpose of tagging equipment is to prevent damage to equip-ment or personnel or to provide supplemental information con-cerning a special operating procedure.
I.4.10.2 Tagging Equipment A. Three tags are provided. See Appendix A for a sketch of ]
the danger tags. The tag color designates its purpose as follows:
Red - Danger to personnel Yellow - Danger to equipment White - Supplemental information concerning an operating procedure Rev. 5/02/89 App'd ljDid SOP /I-14 ]
L _-- -_
B. The Shift Supervisor's approval must be obtained before equipment is tagged.
C. All tags and the tag log must be filled out and each tag ]
attached to equipment by a_ licensed operator. The tag log must contain a description of the equipment tagged, reason for tagging, date, and initials of operator initiating the tag.
I.4.10.3 Removing Tags A. The Shift Supervisor's approval must be obtained before any tag is removed. A licensed operator shall remove each tag ]
and ensure the valve or equipment from which the tag is ]
removed is placed in the proper position or condition. ]
B. When a tag is removed, the date of removal and the initials ]
of the operator clearing the tag shall be entered in the ]
tag log. ]
I.4.10.4 Missing Tags A. Immediately notify the Shift Supervisor in the event a tag is determined to be missing.
B. The Shift Supervisor will investigate the cause of the missing tag and will replace it with a new tag if necessary.
Rev. 5/02/89 App'd SlDM S0P/I-15 ]
L .;
< .a .,
Table III-Normal Reactor Operating' Ranges Parameters. Normal Operating Range Units l
i
-1. Thermal Power, 5 MW Operation 5 5% MW
- 3. Primary Coolant Flow, 5 MW Operation 1850 50 gpm l Primary Coolant Flow,10 MW Operation 3700 50 gpm 4 4. Reactor Outlet Coolant Temperature ' 136 'F
- 5. Reactor Inlet Coolant-Temperature 120 'F
- 6. Pressurizer- Pressure 67 + 3 psig
- 7. Pressurizer Level LENTERLINE + 4 to -8 inches
- 8. Pool Coolant Flow, 5 MW Operation 600 100 gpa Pool Coolant Flow,10 MW:0peration 1200 100 gpa
- 9. Pool Outlet Temperature (Hot Leg) 105 *F
- 10. Pool Level 29' 7" 3" feet-inches ]
- 11. Resistivity, Outlet of DI-300 >500K ohms-cm
- 12. S-1 Temperature Demand Set 120 *F
- 13. S-2 Temperature Demand Set 100 *F Rev. 5/02/89 App'd (dMU SOP /I-16 ]
=__---________
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SECTION II REACTOR OPERATING PROCEDURES 11.1 Routine Reactor Operation 11.1.1 procedure for Reactor Startup For full power operation, the reactor will be brought to its ]
scheduled operating power level acesrding to the procedure out-lined below.
Starting a secondary pump during a normal reactor startup I NOTE:
may reduce primary temperature and pressure to the point that core discharge pressure transmitters 944 A/B may scram the reactor.
A. Take a complete set of full power process data.
B. Obtain from the Shift Supervisor an estimate of the critical banked control blade position.
C. Take a complete set of nuclear data on the Startup Nuclear Data Sheet.
D. Complete the applicable startup checksheet required by Section I (I.4.3.F).
E. Obtain from the Shift Supervisor permission to commence a reactor startup.
F. Announce via the public address system that a normal reactor startup has been commenced.
G. Withdraw the four control blades in gang, stopping to take a set of startup nuclear data at five-inch increments. Indicate in the console log book that startup has commenced.
H. When the blades have reached a position within 2 inches of the estimated critical position, discontinue pulling in gang and take a set of startup nuclear data.
I. Continue the startup, withdrawing only one blade at a time until the reactor power level is increasing on g less_ than I a 30-second period.
J. At a point where the reactor is inaeed critical and on a positive period, a console log entry shall be made stating that fact.
Rev. 5/02/89 App'd IMM SOP /II-1 I ,
K. Bring the reactor critical at a steady state power level of approximately 50 KW unless a lower power level is desired for tests, calibration runs, etc. The lowest steady state power level reached and any ensuing steady state power will be logged on the Startup Nuclear Data Sheet for a record of ;
reactor operating time.
L. Withdraw the fission chamber to full out. L M. Verify that all nuclear instrumentation is responding normally.
N. Take a complete set of nuclear data on the Startup Nuclear Data Sheet. Indicate on this sheet the critical control and reg blade positions and the primary and pool temperatures.
O. Continue the startup, withdrawing only one blade at a time until the reactor power is increasing at no, less_ than a 30 second period. At power levels greater than 100 KW, main-tain the control blades such that the maximum difference in position between any two blades always remains less than 1 inch.
P. As the reactor power level approaches 1 MW, increase the period until a stable period remains that is no, less_ than 100 seconds for all power increases greater than 1 MW.
Q. Bring the reactor critical at a steady state power level of 3 5.0 MW for mode I (10 MW) operation. At this power level: )
- 1. Verify that the nuclear instrumentation is in essential agreement with the actual power level which can be read out directly from the digital calorimetric meter. Ensure ]
that the steady state power level is maintained long ]
l enough for the digital calorimetric meter indication to ]
stabilize (at least five (5) minutes). Note the actual ]
power level in the operations console log book. In the case of the calorimetric meter being out of commission during a startup, the power level may be determined by by manual calculation.
- 2. Note the time of arrival and departure from this power level on the Nuclear Startup Data Sheet.
l R. Continue the reactor power increase by withdrawing only one cont;ol blade at a time, maintaining the reactor period at g less than 100 seconds.
Rev. 5/02/89 App'd V)MY\ S0P/II-2 l-
S. As the scheduled power level is reached, adjust the control blades until the reactor is critical at the desired steady state power in either the manual or automatic control mode.
T. Switch IRM recorder from fast to slow speed and secure the SRM. recorder and scaler.
U. Announce to experimenters the reactor power level, and note ]
arrival in the log book. -]
V. After the temperatures stabilize, take a complete set of ]
nuclear and process data. ]
Procedure for Hot Startup 11.1.2 A hot startup shall only be made by a Senior Reactor Operator, or a licensed Reactor Operator under the direct supervision of a Senior Reactor Operator. Gang control of the rod drives may be used for the entire approach to critical and to override Xenon buildup if required.
A. Take a set of startup nuclear data.
B. Obtain an estimate of the critical banked control blade position from the Shift Supervisor.
C. Obtain permission from the Shift Supervisor to commence a reactor startup.
D. Announce via the public address system that a hot reactor startup has been commenced.
E. Withdraw the four (4) control blades in gang, taking a ]
set of startup nuclear data at five inch increments.
Insure the stable period is no less than 30 seconds. q F. At 50 KW or when channel 1 indication is greater than 10+ 5, withdraw the fission chamber to full out position.
G. Continue the startup, insuring that the maximum difference in position between any two (2) blades always remains less ;
I. than one (1) inch.
i H. Stabilize reactor power at a power level of 5 MW in Mode I. ]
At this power level: 1
- 1. Verify that the nuclear instrumentation is in essential agreement with the actual power level which can be read !
Rev. 5/02/89 App'd dpfA 50P/Il-3 I u __
l l
out directly from the digital calorimetric meter. Note the actual power level and the time of arrival in the
' console log book.
- 2. Note the critical rod heights, power level, primary and pool temperatures, and arrival / departure times on the Startup Nuclear Data Sheet.
I. Continue the raactor startup by withdrawing only one control blade at a time, maintaining the reactor period at no less than 100 seconds.
J. As the scheduled power level is reached, stabilize power in either manual or automatic control and complete the following: 1
- 2. Note the time of arrival in the console log book and in E the Startup Nuclear Data Sheet.
- 3. Announce to experimenters the reactor power level. ]
- 4. Take a complete set of nuclear and process data ns soon ]
as the temperatures stabilize enough to get a representa- ]
tive AT on the primary and pool. ]
11.1.3 Assu;ning Automatic Reactor Control A. Conditions to be met prior to " auto" ope' 9 tion.
Prior to assuming automatic control for reactor operation, the following conditions must be met:
- 1. The period as indicated by both IRM-2 and IRM-3 must i indicate not less than 35 seconds.
- 2. The WRM selector switch must be in the 5 KW red scale position or above.
B
- 3. The power trace pointer (black) on the WRM recorder must E be reading greater than the cuto control prohibits set point (red).
- 4. The reg blade position must be greater than 60% with-drawn, such that 60% annunciator alarm is energized. ,
B. Procedure To place the reactor into the automatic control mode: i Rev. 5/02/89 App'd hM SOP /II-4 I'
J
- 1. Set the low level trip (red pointer) in the wide range recorder so that the auto-control prohibit trip is at 75% of the desired operating power.
- 2. Using the power schedule switch (1S9), bring the setpoint indicator to approximately 3% below a desired power level of > 1000 watts as would be indicated on the black scale of the wide range monitor. l
- 3. Bring the reactor to the desired power level on a period j
> 35 seconds, utilizing the reg blade in such a manner as )
to insure that it is greater than 60% withdrawn when the desired power level is reached.
Note: Caution and good judgement should be exercised on the part of the Reactor Operator when preparing to assume the l automatic control mode in that prior operating experience has revealed discrepancies in readings between the WRM-4 power indication and the demand power for auto control as set by the power schedule switch. The Operator is to be cautioned that the indicated demand power displayed by the power set I meter may lead the WRM-4 power level reading by as much as 5%. This difference is particularly predominant in the lower I percentile range on the meter.
- 4. Depress the blue " auto" control switch S-2 located on the operator console. The " reg rod out of auto" alarm will reset on the annunciator. The reg blade will attempt to reduce the actual reactor power to the level indicated on the power level set meter, by automatically driving down-ward into the core. This initial action on the part of the reg blade is to be observed and verified by the Reactor Operator. Eventually, the reg blade will stabi lite at its critical position, and bring the reading on the wide range recorder into agreement with that as indi-cated by the power level set meter. At this point, the reactor is in automatic control mode.
N_ote: Since the auto control mode was attained at a reactor power = 3% less than the desired level, the difference can now be made up with a slow manipulation of the power schedule switch.
Rev. 10/81 App'd M SOP /II-5
- 5. While closely observing both the reg blade position and the wide range monitor Channel 4 response, raise the power level set until the reactor power stabilizes at a desired level as indicated by the wide range monitor instruments-tion.
To Discontinue Automatic Operation Depress the blue manual switch (S-1). Control will then revert I
to the manual mode and wili be indicated by both the " manual" switch S-1 being lighted and the annunciator alarm " reg rod out of auto" being actuated. .
Manual Override By actuating the regulating rod control switch (ISS), the Opera-tor may override the automatic control system. Operation will E thereafter be in the manual mode unless the operator deliberately E returns the system to the automatic control mode as outlined above. Note: Either a reactor scram or a rod run-in condition will automatically return control to the manual mode.
11.1.4 Procedure for Changing Power Levels For power level maneuvers at powers in excess of 1 MW:
A. Place IRM recorder in fast speed.
B. Take a complete set of nuclear data. ]
C. Place the reactor in the manual control mode by depressing ]
the blue manual switch (S-1). ]
- 1. To increase the reactor power, each control blade or the reg blade may be withdrawn individually until the reactor power level is increasing on no less than a 100 second period.
- 2. To decrease the reactor po;.er, all four control blades may be inserted in gang to reduce power as rapidly as required. However, to recover reactor criticality at I
Rev. 5/02/89 App'd Nbn 50P/II-6 I
the desired power level, each control blade must be withdrawn individually if its position is within 2.00" of its previous critical position. Maintain all blade positions such that the difference in position between any two blades is not greater than 1.00".
D. Recover criticality at the new power level.
E. Replace the reactor control in the automatic node, if desired.
F. Take a complete set of nuclear data.
G. Switch the IRM recorder from fast to slow speed.
H. Record the power change in the log book and on the Startup Nuclear Data Sheet as required.
For power level maneuvers at power less than 1 MW: _
l A. For increasing or decreasing. power, the same procedure as outlined in parts A-H above apply, with the exception that power level increases up to 1 MW may be made on periods no less,inan 30 seconds.
11.1.5 Procedure for Control Blade Shimming s
A. The tutomatic Shimming 'Jnit Can be Considered operational l and will 31.5 the regulating blade out should it reach 5.20", f but it should not be used for routine shimming. f B. For manual shimi.Hnc in auto control, each control blade will be withdrawn or interted individually while the regulating blade automatically adjusts to maintain a constant power ]
I level.
C. The control blade positions will be adjusted such that they all read the same position across the board after the shim-
! ming operation has been completed. 1 D. During the shimming operation, the Reactor Operator will )
closely observe the nuclear instrumentation and the movement of the regulating control blade (when in automatic control),
to verify that the system response to the shimming opercticn !
is normal.
Rev. 12/16/86_ App'd M SOP /II-7 f
_ _ _ - _ - - - )
11.1.6 Reactor Shutdown Procedure A. The procedure for a routine eeactor shutdown requires only that the manual rod run-in cir3uit be activated. However, prior to shutting down the reacter:
- 1. Turn on the source range recorder and time and date the chart.
- 2. Insert the fission chamber until a count of approximately 5
10s cps is obtained on the SRM recorder. B
- 3. Place the IRM recorder in fast speed and time and date the chart. ,
- 4. Take a set of nuclear and process data.
B. Depress the manual rod run-in button on the control console.
Enter the time of shutdown in the log book.
C. Follow the reactor power decrease by changing the range selector switch so as to keep channel WRM-4 on scale.
D. Complete the Reactor Shutdown Checksheet.
E. Ensure that the primary and pool systems are shutdown as per ]
S0P IV.2 and V.2 respectively if the control room is left j g
unattended for an extended period of time. ] m II.1.7 Reductions in Power The procedure for reductions in power to perf orm short evolutions ]
(< 45 minutes) such as Room 114 entry, shall be as follows: ]
A. Turn on source range recorder and time and date chart. ]
B. Inset fission chamber until a count of approximately 10s cps ]
is obtained on SRM recorder. ]
C. Place IRM recorder to fast speed and time and date the chart. ]
D. Take a set of nuclear and process data. ]
E. Depress the manual rod run-in button on the control console. ]
F. Drive control rods in 3" or to a height of 21" withdrawn, ]
whichever corresponds to a lower rod height. ]
G. After evolution is completed, recover power following pro- ]
cedure for hot startur> (11.1.2). ]
H. If the evolution for which the reduction in power is made ]
exceeds or appears that it will extend past 45 minutes, ]
shut down the reactor following procedure 11.1.6. ]
Rev. 5/02/89 App'd MM SOP /II-8 I
I I- 11.2 Fuel Handling Procedure 11,2.1 General A. All fuel transfers will be authorized by the Reactor Manager or.his designated representative.
B. If a fuel assembly is determined by the Shift Supervisor to be damaged, authorization must be obtained from the Reactor Manager prior to loading that element in the reactor.
C. The Special Nuclear Materials Custodian (Reactor Physicist) shall provide a step by step fuel movement procedure anytime fuel is handled.
D. Containment integrity is required any time irradiated fuel is ]
being handled. ]
I E. Fuel, new or irradiated, shall only be handled one element ]
at a time.
F. The reactor will be shutdown prior to handling fuel in the ]
reactor. Fuel may be handled in the weir area while the reactor is operating.
G. Health Physics coverage shall be necessary when the pool is below normal operating level, inspecting irradiated fuel, shipping irradiated fuel and handling suspected ruptured irradiated fuel. i H. One Senior Reactor Operator and one Reactor Operator must be present to handle fuel. Only a Senior Reactor Operatort a ;
Reactor Operator, a Reactor Operator trainee, or Auxiliary Operator under the direct supervision of a Senior Reactor Operator may handle fuel. The Auxiliary Operator will assist in fuel handling only to the extent of passing the fuel ele-ment across the weir divider, and may not_ handle fuel in or out of the core, or in or out of a storage location. The Senior Operator is in charge of the fuel handling evolution and is responsible for the proper conduct of the evolution.
I I Rev. 5/02/89 App'd NQM S0P/II-9 ] 4 l
_ _ - - _ - _ _ _ - _ - _ _ _ - _ _ _ _ - _ _ i
I
- 1. The fuel element fuel plates on the convex and concave ends are very fragile. When moving an element, it is important to approach an obstacle-with the side plate facing the obstacle to prevent accidental danage to the fuel plate.
$1. Two fuel handling tools are available. Normal refueling ]
will be done with the air operated tool and the pool at ]~
normal operating level . If the air operated tool becomes ]
inoperative, notify the Reactor Manager or Operations Engi- ]
neer who may authorire the use of the manually operated ]
fel handling tool as per SMP-17. ]
K. La,,ching and unlatching the air operated fuel handling tool. ]
When latching a fuel element, you will have to get a feel (with practice) for when the tool is in its proper place on
] l the element. Slowly release the air operator handle. The tool will move downward slightly as the tool pulls down ]
into the element. The element should not be considered ]
latched unless the fuel tool makes a discernable drop upon ]
air cylinder actuation. Additionally, verif_y the element is ]
latched by observing that the red indicator on the horizontal cylinder is fully retracted. When unlatching the element, push down on the tool while slowly pushing down the air operator handle to the locked released position. When in the reactor, never lift the tool off the element. Always allow the tool to float up off the element. It will not float up if the element is attached but can easily be worked off the element by pushing down and turning until it floats off. 1 4
Failing to release the element in this manner may result in accidentally lifting and leaving the element a few inches off J
of its seated position without realizing it. I l
l i
I i Rev. 5/02/89 App'd UlDdl SOP /II-10 ]
I
1 I
! 11.2.2 Procedure for Handling Fuel In or Out of the Core
[ .
A. Obtain a fuel handling sequence from the Reactor Physicist.
l B. Inspect the fuel handling tool. Check both the physical ]
latching mechanism and the proper indication for the un- ]
latched condition of the tool. ]
C. Place the bridge ARMS to upscale position.
D. Insure the pool is at the normal operating level. ]
l
'l E.
F.
Remove the pressure vessel head.
Turn on the Source Range Monitor Scaler and Chart Recorder.
i Drive in the fission chamber to = 1000 counts.
G. Attach a fuel element to the handling tool .
H. The operator handling the fuel element tool shall verify that the element is fully latched and verbally report this to the supervising Senior Reactor Operator.
NOTE:
A positive latch is achieved only after noting a discernable ]
drop in the fuel tool upon air cylinder actuation and when ]
the red plunger on the air-handling tool is fully, retracted and flush with the end of the cylinder. Any protrusion of ]
the plunger means the fuel element is not properly latched. ]
- 1. Remove and visually identify the fuel element and place it in the position specified on the loading sheet.
J. A Reactor Operator or Maior Reactor Operator shall initial I the loading sequence sheet after each step.
]
K. Verify the elements in the reactor are seated, using the board and reference mark. ]
L. Perform a post-refueling map check, verifying that the appropriate positions in the "X", "Y" and "Z" h?. sets contain fuel elements as indicated on the post fuel handling sequence drawing.
M. A Senior Reactor Operator will inspect the core prior to replacing the pressure vessel head.
I Rev. 5/02/89 App'd M SOP /II-11 ]
l
y o l N. Install the pressure vessel head. (If the pressure vessel head is to be left off at 'this point, install the aluminum protective head on the pressure vessel.) { '
- 0. Record that the reactor has been defueled or refueled indicating the identification numbers of the cores involved and the fact that the new core has been inspected. The Senior Operator inspecting the core will initial this entry. ]
P. Post the fuel element locations data sheet in the control ]
room. .]
Q. The SRM may be secured and the fission chamber pulled full ]
out, once refueling is completed. ]
II.2.3 When starting up the reactor after any fuel change in the core, the predicted critical position shall be verified by the Reactor g Physicist If the reactor has been loaded with a new mixed core, E a 1/M plot shall be made on the subsequent start-up.
11.3 Control Blade Offset Mechanisa Removal 11.3.1 Conditions Prior to Removal A. The control rod offset mechanism will not be removed except by authorization of the Reactor Manager.
B. The removal of the assembly will be supervised by the Shift Supervisor or a Senior Operator.
C. When one offset mechanism is to be removed:
- 1. The core will be defueled of two fuel elements;
- 2. The balance of the other three rods will not be raised from their fully lowered position without approval of the Reactor Manager.
D. When more than one offset mechanism is to be removed, the core will be defuelee of at least two elements for each offset mechanism removed.
E. A Health Physicist or a Health Physics Technician is to be present when the pool water is lowered and when the mechanism is brought near the surface of the pool or out of the water. ]
Rev. 5/02/89_ App'd WT)M SOP /II-12 ]
I .
______.____..__.._._____s
- s. .
, 'Y.
4 N .
F. :During the process of actually removing the offset,' the core
-neutron levels'will. be. continually monitored using the
- fission-pulse channel SRM-1. The . reactor control room may be unattended during the removal operation. All reactor s ' systems will be shutdown.
11.3.2 Caution Should;be Taken During Removal as Follows:
A. Due to the potentially high radiation level produced' by. the activated blade, place the bridge ARMS to the upscale posi-
~
. tion to prevent a building isolation alarm while the offset ] .-
I '
is being handled near-the surface of the water. ].
B. . Extreme caution should be used during Step II.3.3.L so that undue _ stress is_ not placed on offset mechanism while breaking it loose from guide pins. Also,' extreme caution should be .
used while maneuvering the offset mechanism away from the pressure vessel.
~
II.3.3 . Th'e Detaile'd Procedure for' Removal is'as Follows:. l l
A. Electrically.' disconnect the rod drive mechanism.
B'. Remove the four bolts at the base of the rod drive mechanism and with either the rod magnet fully inserted or withdrawn, remove the rod drive mechanism.
C.- Remove the four bolts at the base to the rod drive shaft
, housing assembly.
D. Mark position of photocell housing for drop timers / rod ] .j bottom indication and remove. ]
E. Remove the "U" clamp attaching the upper housing to the ;
bridge floor plate.
F. The upper housing unit may now be lifted free. Mark the :
upper housing when more than one mechanism is to be removed..
G. Loosen the bolts on the lower housing bracket and remove i same.
l Rev. 5/02/89 App'd {A)QfY\ S0p/II-13 ]
i H. Unscrew. lift rod assembly and lift up as far as it will go. g Remove lift rod and lower housing as one unit, j I. Using bolt removal tool, loosen offset mechanism hold down bolt on rear of assembly. l J. Insert offset mechanism pulling tool into hole in counter ,
balance arm and raise blade to full out. Insert "T" section of lift tool into lifting lug at top rear of offset.
K. Attach the lifting tool to the crane.
L. Jog the crane while lifting by hand until the offset mecha-nism lifts free of the side guide pins. Observe closell the strain necessary to break the offset free. If the offset mechanism does not break loose from its reflector platform after applying a reasonable amount of tension, relieve the tension on the lifting tool and determine the reason for the difficulty before continuing the attempt to lift the mecha-nism.
M. After the offset mechanism has cleared the guide pins, care-fully raise it until the top of the blade mount is about 1/8" below the pressure vessel intermediate flange.
NOTE: After the mechanism clears the guide pins, the blade is still partially within the gap so caution must be observed to hold the mechanism steady while raising it to the flange above or the blade may be damaged.
N. With the blade now clear from its gap, carefully move the mechanism away from the pressure vessel " spool" flange and raise the mechanium to the surface.
CAUTION: The lower portion of the mechanism and the lower tip of the blade will be very radioactive, so insure close Health Physics coverage is pro-vided before raising the blade to the pool water l surface.
Rev. 5/02/89__ App'd M\ S0P/II-14 ]
Reset i
11.3.4 Installation of the Control' Blade Offset Mechanism The procedure for installing the blade and offset mechanism is essentially the reverse of the above, with a particular emphasis on the following points:
A. Before inserting the mechanism, check the clearance of the blade gap with the gapping tool.
B. . After disengaging the lifting tool from the locking "T", the Shift Supervisor or Senior Operator will exercise the blade
~ over its full- length of travel until he is convinced that the blade moves freely and is able to travel through the gap totally without resistance.
C. During the subsequent pull for the rod drop test, determine ]
the position at which the photocell for the drop timer ]
actuates with respect to the blade full-in position. It ]
must not be greater than 5.2".
II.4 Waste Tank Analysis ] i A waste tank analysis is performed by the laboratory group for i
evidence of activity prior to release to the sanitary sewer.
See Section VII.8.6. A pH of each sample is measured to ]
determine its acidity. If the waste water is very acidic (pH I less than 4) and the liquid waste is to be held, a caustic solution should be added and circulated to prevent excess corrosion of the waste tanks.
I I .
I Rev. 5/02/89 App'd M SOP /II-15 ]
l 11.4.1 Taking a Sample ]
Normal water samples taken for water chemistry shall be taken in ]
a 500 ml capped poly bottle. The WT and secondary samples ]
require 1 liter samples. An additional 100 mi sample should be ]
drawn in a urine sample bottle for all WT samples and for any ]
secondary sample that requires radiochemical analysis. ]
A. Rinse and clean the sample container with DI water. ]
B. When taking the sample, purge the sample line to rid any ]
stagnant solution.
C. Fill the sample container completely. Do not permit the
]
']
l sample to be air mixed while drawing the sample. ] -
D. Cap the container immediately to prevent atmospheric ]
contamination. ]-
E. Note the time, date and source of the sample. ]
I-I i
Rev. 5/02/89 App'd W 50P/II-16 ]
~ '
A SECTIONLIIIi y b , REACTOR CONTROL AND. INSTRUMENTATION' SYSTEM III.1- Preparation.of Reactor-Instrumentation for Operation 111.1.1' General
~
Power to the process. instrument panei'is provided by the. 480 V
. circuit through a step down-transformer located behind_the' panel' .
Power..to the process panel including the neutron monitoring.
equipment will be maintained continuously. Adjustments and calibrations other than outlined in this procedure will be per- ,
I formed by; a'. licensed Reactor Operator or an Electronics Tech- '] ;
nician.
After any maintenance is performed on. a Nuclear Instrumentation 4
- detector or its associated cables, that channel of N.I,'s shall be_ response checked before commencing.a reactor startup. The response check can be performed with either a gamma or neutron source. The. successful response check shall be noted in the control room log book.
111.1.2 Procedure for Securing Electrical Power to Console and' Instru-l ment Panel NOTE: ot remove detectors from
" STANDBY" position does ,n,o,t, ]
ci rcuit. Electrical transients in this mode may result ]
in damage to detectors or high voltage power supplies. ] j A. Place all N.I. drawers to zero/zero 1. -] ]
l B. Remove VR units from N.I. drawers.
C. Turn Power Switch to "0FF" on 2PS1 and 2PS2. ]
f' D. Turn Power Switches 2CB1A and 2CB1B to "0FF". )
E. Prop open back-up doors. !
F. On Emergency Lighting Panel:
- 1. Open E15 5 2. Open E18 J G. Place Elgar Line Conditioner Switch to "0FF".
Rev. 5/02/89 App'd bJh% SOP /III-1 ;
I.
__ _ - a
'i l
4 III.2 Front Panel Checkout of Source Range Monitor Channel 1 1 m
A. Verify that.the power to the recorder is on.
B. Set the function switch to " operate".
C. Verify that " drawer inoperative" lamp on the front panel of the module is extinguished.
D. Set function switch to " standby". Verify that the " drawer inoperative" lamp is glowing and that the " instrument anomaly" illuminates on the annunciator board.
E. Set function switch to "zero". Verify that the "down-scale level" trip indicator' is glowing, that the LCR meters and ]
recorder both indicate 10-1 and that the " period" meters indicate -30 seconds.
F. Set function switch to 10 s. Verify that the LCR meters and recorder indicate 8 x 104 - 1.5 x 10 5 and that the "down-scale leval" trip goes out.
G. Set function switch to 10. Verffy that LCR meters and the recorder indicate 9.8 - 10.2.
H. Set function switch to " period" position, and " ramp" switch to " fixed". Verify that " period" meters indicate +3 seconds.
I. Release " ramp" switch, turn " reset" switch to " ramp" posi-tion for about two (2) seconds, and set function switch to
" operate" position.
J. The SRM is now ready for use. Reset the annunciator.
K. Turn on scaler power.
Note: The scaler readout mode is to be set at the discre-tion of the startup operator.
III.3 Pre-startup Check of Intermediate Range Monitor Channels 2 and 3 A. Verify that power to the recorder is on and that the IRM recorder selector switch on the control console is in position 2 or 3 as required.
B. Set function switch to " operate".
C. Verify that " drawer inoperative" (DS16A) lamp is extin-guished.
D. Verify that " period trip" lamps are extinguished.
l Rev. 5/02/89 App'd Mr&M SOP /III-2 l
i E. Set function switch to " standby". Verify that the " period trip" indicators are not glowing.
F. Verify that lamp DS16A is glowing and a Nuclear Instrument ,
Anomaly annunciation occurs.
G. Set function switch to zero No. 2. Verify that the ampere meters and recorder all indicate 10-10 and the " period" :
meters read -30. l H. Set function swio... to zero No. 1. Verify that the ampere meters and racorder all indicate 1G-10 and the " period"
(
meters read -30.
I. Set function switch to " period". Hold " ramp" switch to {
" fixed". Verify that " period" meters indicate +3 and
" period trip" lamp (DS17A) lights. <
J. Release " ramp" switch. Move " reset" switch to the " trip" j position, then hold it in the " ramp" position until ampere meters indicate 10-10; then release " reset" switch. !
K. Set function switch to the 10-8 position. Verify that the I
ampere meters and the recorder all indicate 8 x 10-9 to 1.2 x 10-8 L. Set function switch to the 10-4 position. Verify that the ampere meters and recorder all indicate 8 x 10-5 to 1.2 x 10-4 M. Set function switch to 1.5 x 10-3 position. Verify that the ampere meters and recorder all indicate 1.2 x 10-3 to 1.8 x 10- 3 N. Set function switch to " period" position.
O. Hold " ramp" switch (S3) to " variable".
- 1. Verify that when the control console period meter reads 11 21 seconds, the short period rod run-in lamps (DS17A) lights and short period rod run-in annunciation occurs.
- 2. Verify that when the control console period meter reads 9 1 seconds, the short period scram lamp (DS16B) lights and the short period scram annunciation occurs.
P. Turn reset switch to " ramp" for approxim.stely 2 seconds, then to trip and release.
Rev. 10/81_ App'd WM SOP /III-3
Q. Place function switch in " operate" position.
R. Set compensation voltage so that indication is >10-9 if possible. -
S. Reset annunciator on control console.
T. This IRM is now ready for operation.
111.4 Prestartup Check of Wide Range Monitor Channel 4 -
A. Record the last heat balance setting of the drawer potenti-ometer. Compare potentiometer setting with last recorded heat balance setting.
B. Verify that power to the recorder is on. Time and date the chart if necessary.
Set function switch to operate and momentarily rotate C.
" reset" switch (S2) to left or right.
D. Verify that " drawer inoperative" indicator (DS16A) is out.
E. Set function switch to " standby". Verify that " drawer inoperative" light (DS16A) is energized and that a nuclear instrument anomaly occurs.
F. Set function switch to zero No. 2. Verify that the power meters and recorder indicate 0 2 and that "downscale trip" light (DS17B) is energized and a downscale alarm is received on the annunciator.
G. Set function switch to zero No. 1. Verify that power meters and recorder both indicate 0 2% and that "downscale trip" light (DS17B) is energized and a downscale alarm is received on the annunciator.
H. Momentarily rotate " reset" switch to left or right to clear rod run-in and scram trips.
I. Set function switch to " trip test".
J. Using the variable pot on the front of the module drawer, set trip adjust potentiometer to obtain an indication on the front panel meter equal to 114% t 1%, the desired set-ting for rod run-in. Verify that rod run-in light (DS17A) l is energized and that Channel 4-5-6 High Power Rod Run-In Rev. 10/81 App'd NhTT\ S0P/III-4
p l'
annunciation occurs. Also verify the correct response of
- the console power meter and recorder at this signal level.
L '- K. Set trip adjust potentiometer (R1) to obtain an indication on the front panel meter equal to 119% 1%, the desired setting from High Power Scram. Verify that scram light L (DS16B) is energized, and that Channel 4-5-6 High Power Scram annunciation occurs. Also verify the correct response of the console power meter and recorder at this signal level.
L. Return meter reading to less than 115%.
M. Set function switch to operate. ;
N. Clear rod run-in and scram trips by rotating " reset" switch to left and right.
O. Reset the annunciator.
P. WRM-4 is now ready for operation.
III.5 Check of Power Range Monitor Channel 5 and 6 A. Select Test / Feedback Module corresponding with the node of I operation intended (the modules are marked and color coded with the colors used on the Mode Indicating Lights) and place the correct module in the drawer.
B. Place the Power Selector Switch 158 in the applicable 4 position for the operation intended.
C. Record the actual setting of the drawer amplifier feedback potentiometer on the Startup Nuclear Data Sheet.
D. Set the potentiometer to the calibration value determined'by the Electronics Technician and marked on the potentiometer.
E. Set function switch to " operate". Verify that " drawer inoperative" lamp is extinguished.
F. Verify that power level trip indicators are extinguished.
G. Set function switch to " standby". Verify that power level trip indicators are extinguished, that " drawer inoperative" light (DS16A) is energized, and that a nuclear instrument anomaly annunciation occurs.
I Rev. 10/81 App'd NM S0P/III-5 i
L I H. Set function switch to "zero". Verify that both percent power meters (on the console and instrument cubicle) and the recorder indicate 0 t 2%. Verify that a downscale light ,
is received on the drawer and that a downscale alarm is received on the annunciator.
I. Set function switch to 110%. Verify that the console percent power meter and the recorder indicate 110% 2% and the drawer meter indicates 110% 5%.
J. Set function switch to 75%. Verify that the console percent g power meter and the recorder indicate 75% 2% and the drawer 5 meter indicates 75% 2 5%.
K. Set function switch to 10%. Verify that the console percent power meter and the recorder indicate 10% 2% and that the drawer meter indicates 10% 5%.
L. Place function switch it " cal" position. Rotate reset switch to left or right to clear rod run-in and scram trips.
Reset annunciator board. Using the potentiometer provided on the front of the drawer, apply an input current equivalent to the desired trip point for rod run-in (114% 1%). Verify that rod run-in light (DS17A) is energized and that Channels 4-5-6 High Power Rod Run-In annunciation occurs.
M. Apply an input current equivalent to the desired trip point for scram (119% 1%). Verify that scram light (DS16B) is energized and that Channels 4-5-6 high power scram annuncia-tion occurs.
N. Return test signal to minimum setting. Set selector switch to operate.
O. Rotate reset switch to reset position and release. Verify that all trip indicators are extinguished. Reset the annunciator.
P. Set the potentiometer to the setting corresponding to the last value determined by heat balance. This should be the setting determined in Step A.
Q. This PRM is now ready for operation.
Rev. 7/30/85_ App'd NM SOP /III-6 I
- )
i I
Ill.6 Procedure for Physically Adjusting NI Detectors at Power Caution A. The aluminum clad lead shield for the detector cables makes the dry wells very heavy and difficult to handle. Be extremely careful to hold the dry well firmly while the j clamps are being loosened. The crane and a rope may be i
used to support the dry well during this evolution, but ;
i NEVER raise the well with the crane. When raising a dry ;
well, lift it by hand and then restore the rope tension with the crane.
B. Physical movement of an NI detector dry well will usually affect the readings of adjacent channels,
\
b 111.6.1 Adjusting Channels 2 or 3 NOTE:
I This procedure calls for extreme caution as a small step change can induce short periods with a resulting run-in and/or scram.
A. Place IRM recorder to fast.
B. Place IRM selector switch to channel not being adjusted.
C. Adjust channel.
D. Place IRM recorder to slow.
E. Log change.
111.6.2 Adjusting Channels 4, 5 or 6 NOTE: If reduction in power may result in an inability to ]
override Xenon and recover to 10MW, the adjustment ]
can be done at 10MW with Reactor Manager permission. ]
A. Reduce power to about 9 MW as per 11.1.4 Procedure for ]
I Changing Power Levels. ]
B. Maintain power at 9 MW in manual control. Use Channel 5 for control if Channel 4 or 6 is being adjusted and use Channels 4 and 6 for control if Channel 5 is being adjusted.
C. Place the pot of the channel being adjusted to midrange.
D. Adjust the detector position to place the channel at the desired level .
Rev. 5/02/89 App'd \))tWY\ SOP /III-7
i:
l 1
I E. Increase power to original level.
F. Log final new pot setting.
I III.7 Check of Process Dadiation tionitors 111.7.1 Operational Check of Fission Product and Secondary Coolant E~
Monitors W A. Set function switch to operate.
B. Verify that drawer inoperative lamp is extinguished.
C. Set function switch to standby. Verify that the drawer g inoperative lamp (DS16A) is energized. E D. Set function ' switch to zero. Verify that the front panel meter indicates 10-1 20%.
E. Set function switch to 105 . Verify that the front panel meter indicates 105 20% and the respective hi activity annunciator channel trips.
F. Set function switch to 10. Verify that the front panel i meter indicates 10 20%.
G. Set function switch to operate.
111.7.2 Operational Check of Stack Monitor A. The operator conducting the test in the West Tower shall establish communication with the control room via the intercom. ]
B. Place the mode switch for the iodine detector in the "T" (test) position.
C. Verify that the recorder pen indicates 3600 cpm 10%, and that the stack monitor high activity annunciation is re-ceived. 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 down-scale position. Reset the annunciator.
F. Place the mode switch for the particulate / gas monitor in the "T" position, j l
Rev. 5/02/89 App'd UO0rM SOP /III-8
G. Verify that the particulate recorder and gas recorder pens indicate 3600 cpm 210% and that the stack monitor nigh I- activity annunciation is received. Also verify that the local meter reads within 10% of the test reading marked on the meter face.
H. Return the particulate mode switch to "0P" position.
I. Press the " reset" button until the particulate meter and recorder readings return to normal; do not drive it to the downscale position. Reset the annunciator.
J. Test the low flow alarm in the control room by securing the ] i blower. ]
I K. Return the blower switch to "on", verify "high" and' " low" ]
alarms cleared. ]
III.8 Area Radiation Monitoring System The area radiation monitoring system will be in operation con-I tinuously 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 South Wall 2 X acceptable background Station 2-BP West Wall 2 X acceptable background Station 3-BP North Wall 2 X acceptable background Station.4-Fuel Vault 10 mr/hr Station 6-Room 114 2 X normal operating background I Station 7-Reactor Exhaust Plenum 1 mr/hr or 10 X normal opera-ting background Station 8-Reactor Bridge 50 mr/hr or 10 X normal opera-ting background Station 9-Reactor Bridge Backup 1 K - 10 K mr/hr At least once per month the system will be checked according to the following procedure.
Rev. 5/02/89 App'd UjhTV\ S0P/III-9 I
A. Insure that power is on. Power should be on at all times.
B. Using the master meter on the power cnd control unit, verify -
that the alarm relay voltage is
+150VDC{j0 and the high voltage is set at 520 10 VDC.
C. Place channel selector switch on position 1.
D. ' Operate the check source push button and verify that when the trip point is reached, the power and control unit alarm lamp lights and the unit audibly alarms and also the probe alarm l
lamp (Beam Hole Floor South) lights and it too gives an audible indication if applicable. The trip setpoint is lowered by a mechanical adjustment button at each meter.
E. Set trip point back to original setting.
F. Repeat steps C through E for Channels 2, 3, 4, and 6 g observing that the lamps on the power and control unit and 5 the individual stations illuminate and give an audible indication.
G. The source check of Channels 7, 8, and 9, while performing ]
the above-mentioned functions, also initiates a reactor scram and produces a containment building isolation.
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 the horns silenced and the isolation valves and doors closed.
l H. To conduct source checks of Channels 7, 8, and 9: ]
- 1. Select desired channel; check trip point setting.
- 2. Reset scram and rod run-in trip actuators.
l
- 3. Notify all persons within the facility of intentions to perform the check.
l Rev. 5/02/89 App'd \hC% SOP /III-10
)
4 j
4
- 4. Press source check push button and monitor point of trip,
~
verifying the following to have occurred:
- a. Scram and rod run-in trip actuator amplifier tripped.
- b. Building air plenum high activity scram alarm indicated on annunciator.
- c. Evacuation or isolation scram alarm indicated on annunciator.
- d. 16" isolation valves indicate closed.
- e. Containment isolation horns have sounded.
- f. Isolation doors M0-504 and M0-505 indicate closed.
- g. Supply and return fans have secured.
I h. Red flasher light outside outer containment door is flashing.
- 1. Alarm buzzer on ARMS module is alarming.
- 5. If more than one check is required,
- a. The horn cutout switch may be used to silence the containment horns,
- b. The 16" isolation valves cutout switch may be turned to the off position, leaving the valves closed.
- c. The motor operated isolation doors may be left in the closed position.
- 6. When the checks have been performed as required, reset I the tripped Channel 7, 8, or 9 trip.
Trip the backup door radiation monitor with the attached
]
7.
source. (Trip set pointer may have to be lowered to ]
obtain trip.) Verify that the items m 4 above are ]
initiated by the monitor trip. (Return trip set pointer ]
to proper setpoint if moved.) ]
- 8. Close the 16" isolation valve cutout switch, verify the valves indicate open.
- 9. Open isolation doors M0-504 and M0-505 by depressing the I open push button for 5 seconds after the fans start.
- 10. Perform the visual inspection of the ventilation system l I' on the fifth level.
- 11. Turn the ARMS detector channel selector switch to Channel 5.
Rev. 5/02/89 App'd [dDm 50P/III-11
I I,'
- 12. Insure isolation horn cutout switch turned on.
NOTE: If additional ARM checks are to be made, repeat steps A through C.
- 13. Notify all person within the facility that checks are completed and that they should regard all further alarms.
I I'
I l
I I
I Il Il I
Rev. 10/81 App'd NQp\ 50P/III-12
SECTION IV PRIMARY COOLING SYSTEM IV.1 Startup of Reactor Cooling Loop IV.1.1 Procedure A. Prior to placing the primary system on the line:
- 1. Verify that no primary system maintenance has been performed since the last shutdown of the primary system.
If maintenance has been performed on the system, insure that all valves disturbed are in their normal positions.
The Shift Supervisor will determine if a valve lineup checksheet needs to be completed.
' Note: For Mode II or III operation, close the inlet valve (510B or 510F) of the heat exchanger not being used and tag out the pump breaker which will not be used.
- 2. Verify the proper lineup of the following systems in accordance with their respective 50P sections:
I
- a. Nitrogen and Air System - Section VII.9 and 10
- b. Demineralized System - Section VII.4
- c. Primary / Pool Drain Collection System - Section VII.6
- 3. Verify or perform the following:
- a. P501A/B shaft cooling water supply valves are open.
- b. There are at least 2000 gallons of water in T300.
- c. Power is available to P501A/B, P533 and P513A.
- d. Primary system flow recorder and temperature recorders are energized and the primary demineralized flow recorder is energized. Time and date-the recorders.
- e. Place heat exchanger bypass switch 2S41 in the position required for the ce.a. exchanger combination to be used.
Rev. 10/81 App'd NIM \ SOP /IV-1
B. Verify antisiphon vent valve closed.
C. Verify antisiphon system manual drain valve closed.
D. Set the antisiphon system air regulator to 35 psig and open the air inlet valve.
E. Place master switch 151 to test.
F. Open valves 527E and F.
G. Place valve 545 switch to auto / closed.
H. Place valve 527A switch to auto / closed.
I. Place valve 5278 switch to auto / closed.
J. Place pump P-533 switch to auto, P-533 may or may not start, depending upon demant K. After P-533 has completed charging, place valve 526 switch to auto / closed.
L. Place valve 507A/B switch to manual /open. Valves 543A/B will automatically close at this time.
J M. Immediately place valve 527C switch to open. The primary system is now pressurized.
N. Cycle valves 546A/B switches to manual / closed.
O. Immediately start pump 501A or B. Verify proper flow.
P. Cycle valves 546A and B onan and then closed one at a time and verify the increase and then decrease in primary system flow indicated by changes on DPT-929 or PT-944 A/B as each ]
valve is cycled. ]
Q. Start the remaining pump 501A or B. Verify proper primary system flows.
R. Start pump 513A and verify proper flow.
S. Open the antisiphon system drain valve and blow the system dry. Close the valve, wait 10 seconds and repeat. This may f have to be done three or four times to insure that all the water is drained.
T. Close the antisiphon system drain valve.
U. Insure that the antisiphon system pressure is between 35-40 psig; then close the air inlet valve.
Rev. 5Z02/89 App'd dbdY\ SOP /IV-2 h . _ _ _ _ _ _ _ _ _ _
h c.
V. : Place'the' following valve controls in the indicated positions:
Valve ' Mode' Position' Valve Mode Position
.V507A/B' Auto. Closed V526 Auto Closed iJ .V546A/B ' Auto. Open V527A Auto Closed
-V543A/B" --
Open- -V527B: Auto Closed Auto Closed .Open-
^
V545- V527C --
.W. Verify that all the ' valve position indicating lights are operating with the valves in the positions listed in Step y.
If not, replace the appropriate light. bulb.. If'this does not' clear the malfunction, shutdown the primary system as I per IV.2'and. verify proper valve operation by a visual.
. examination of the actuator. linkage during operation. In the case.of.V543A or B indication failure, perform CP-24~
Compliance Check; NOTE: If the malfunction is determined to be an electrical'
' indication problem not used in the sr.fety system, -l the reactor may be operated with regairs being j made at the next maintenance shutdown. ;
X. For 10 MW, 2 pump operation, balance loop flows as follows: -l 1.. Check the flow in the' two heat exchanger loops and ]
adjust.the 540 valves to' balance the flow. l
-2. Check the oP r; oss each of the pumps and adjust the j
- bypass valves to balance the flow delivered by each pump.
l IV 2 Shutdown of Primary System ,
t
'l NOTE: The primary system should remain in operation for fifteen j minutes after reactor shutdown to remove decty heat.
IV.2.1 Procedure j i
l A. Place master switch ISI in test. !
B. Close valve 527C. j C. Secure pump P533.
D. Secure'P513A. ,
E. If both pumps P501A and/or P501B are running, secure them simultaneously to reduce check valve slam.
Rev.' 10/81 App'd [dlym SOP /IV-3 ,
i
F. Verify that valves 546A/B open on the loss of flow. '
G. Place the 507A/B mode switch to manual.
H. Verify that V507A/B close and that valves 543A/B open.
I. Open the drain valve on the antisiphon system and then slowly open the vent valve and bleed the pressure to zero. Reclose the valves when depressurized.
J. Place the following valve controls in the indicated positions:
Valve Mode Potition Val v__e Mode Position V507A/B Manual Closed V527A Manual Closed
.V546A Manual Open V527B Manual Closed ,
V546B Manual Open V545 Manual Closed V543A/B -- Open V526 Manual Ciosed K. Verify that valves 507A and B have operated and sealed closed by cycling V507A/B while noting the system pressure drop.
There will always be some pressure drop due to pressure trapped on the pump side of V507A/B; if not, repair of V507A or B actuator or valve is required prior to any reactor start-up.
L. Llose valves 527E/F.
M. Verify that all the valve position indicating lights are operating with the valves in the positions listed in Step J.
If not, replace the appropriate light bulb. If this does not clear the malfunction, determine the cause and make repairs prior to any reactor startup. For V543A or B, perform CP-24 Compliance Check. ,
NOTE: If the malfunction is determined to be an electrical indication problem not used in the safety system, the reactor may be operated with repairs being made l at the next maintenance shutdown. ]
NOTE: The following are at shift supervisor's discretion. ]
N. Secure the primary flow and temperature recorders and the j primary demineralized flow recorder. Time and date the I recorders. 4
- 0. Secure power to pumps P501A/B, P513A, and P533. I P. Secure shaft cooling water supply to pumps P501A/B.
Rev. 5/02/89 App'd 4}(NY\ S0P/IV-4
m-t' IV.3 Operation of the Antisiphon System f
IV.3.1 General Operating Philosophy The antisiphon. system is designed to provide sufficient air (under pressure) to break a siphon of the primary coolant system in the event of a pipe rupture. To perform its function, this system must be maintained at a pressure greater than 27 psig, and the water level above the antisiphon valves must be less than six inches. The procedures below will be followed to insure that the antisiphen system is operated within the above limitations.
L IV.3.2 Decreasing Pressure in the Antisiphon System The system contains a pressure switch which will initiate an annunciator alarm when the system pressure falls below 30 psig.
Upon receipt of the low pressure alarm an attempt shall be made to establish norma,1 system pressure by admitting air through the air valve and regulator on the bridge. If system pressure cannot be maintained above 27 psig, the reactor shall be shutdown until the problem is corrected.
IV.3.3 Increasing Pressure in the Antisiphon System
)
After the primary coolant system has been placed in service, open g
5 the system drain valve and check that the system is drained of all water. The system's pressure will then be returned to the middle of the operating band (~36 psig) and this pressure will !
be recorded on the routine patrol sheet.
I On each subsequent routine patrol, read the system pressure 1
and compare it to the base pressure recorded after the startup.
If the pressure has increased by more than 4 psi, action must be ]
taken to insure that the pressure increase is not due to in- )
I leakage of primary coolant water. If the pressure has increased by more than 4 psi, carry out the following procedures: )
I A. Open the drain valve and observe the water flowing from the drain line. 1 I I Rev. 10/81 , App'd M SOP /IV-5
- I B. Drain until you no longer receive a solid stream of water, then close the drain valve.
C. If the amount of water drained is significant, record this fact on the routine patrol sheet and in the console log.
D. Return the system pressure to normal (~36 psig) by venting or adding air.
E. Record the new base pressure on the routine patrol sheet.
A new base pressure will be established during the first routine patrol of every day that the reactor is operating. To establish the new base pressure, carry out steps A through E above.
IV.3.4 Antisiphon High Level If an antisiphon high level rod run-in is received, carry out steps A through E of IV.3.3. When the high level alarm has cleared,-the rod run-in may be reset. Do not withdraw rods until a thorough check of the system has been made to determine the source of the water leak..
IV.4 Depressurization of Pressurizer IV.4.1 Procedure A. Shutdown primary system in accordance with Section IV.2. ]
B. Place valve position switch for V545 to open.
C. Allow pressure in pressurizer to reduce and then place valve position switch for V545 to close.
IV.5 Isolation, Draining, Filling and Normal Operation of Primary Heat Exchanger Loops - Moved to SMP-18. ]
IV.6 Isolation, Draining, Filling and Normal Operation of Primary Pump Loops - Moved to SMP-19. ]
I Rev. 5/02/89 App'd (NM\ SOP /IV-6
L ;
SECTION V !
\
'I POOL COOLING SYSTEM V.1 Pool Cooling System Startup V.1.1 If pool system maintenance has been performed since the last pool system shutdown, insure that all disturbed valves are in their normal positions. The Shift Supervisor will determine if a valve l lineup checksheet needs to be completed.
V.1.2 For Mode I operation, both heat exchangers 521A/B and either one ]
or both pump (s) 508A/B must be in operation. ]
I' -V.1.3 When the appropriate position for the pool system valves has been established, then the pool system can be started up according to the.following procedures:
A. N2 and air system should be in service (SOP VII.9.2 & ]
VII.10.2). ]
B. Visually check for a proper pool level; the pool should be filled to a level satisfying either LC-910 (normal pool level controller) or LC-966 (intermediate refuel pool level I' controller).
C. Check that reflector & scram setpoints are set for the ]
I mode of operation planned.
I I Rev. 5/02/89 App'd hW SOP /V-1
D. Visually check for proper in-pool loadings:
- 1. Make certain experiments are securely loaded and are m seated within their proper loading facilities.
L 2. Make certain the flux trap facility appears normal and the test hole strainer is properly in place, or the test hele sample holder is correctly and securely positioned. ]
E. Turn on the pool flow and temperature recorders and time and date.
F. Verify that the local pump stop switches in room 114 are unlocked.
NOTE: If the breaker is closed, the selector switch is in the auto mode and the stop switch is unlocked; the off indicator in the control room for P508A/B will be lighted.
G. Place HX bypass switch 2S40 in the position required for the HX lineup intended.
H. Master control switch IS1 should be in the test position.
I. Place valve V509 switch to the manual /open position.
J. Turn on pool pump P508A/B as appropriate by turning the !
control switches to on. Verify proper flow.
K. Start cleanup, pump P513B and verify flow.
L. Adjust pool flow if required by throttling the HX outlet valves (522A and 5220) as necessary.
M. With normal flow and pressure, place V509 switch to auto /
closed. j N. Verify that all the valve position indicating lights are operating. If not, replace the appropriate light bulb.
If this does not clear the malfunction, shutdown the pool system as per V.2 and verify proper valve operation by a visual examination of the actuator linkage during operation.
NOTE: Determine the cause of the failure and make repairs prior to any start up.
O. If not required for other evolutions, turn master control switch 151 to the on position.
Rev. 5/02/89 App'd WQTY\ S0P/V-2
V.2 Pool System Shutdown Procedure 1
i V.2.1 The pool cooling system should remain in operation for a short
]
period of time (5 minutes minimum) after a normal reactor shut- j down in order to remove core decay heat from the reflector and experimental facility. The procedure for attaining a normal pool system shutdown mode is as follows:
A. Place master switch 151 in test.
B. Turn off cleanup pump P513B.
C. Turn off P508A/B using the control switches in the control room. To minimize check valve slam, secure both pumps simultaneously.
D. Verify that valve V509 closes automatically.
E. Place V509 in the manual / closed position.
F. Verify that all the valve position indicating lights are operating. If not, replace the appropriate light bulb.
I If this does not clear the malfunction, determine the cause and make repairs prior to any reactor start up.
NOTE: The following steps are at Shift Suprvisor's discretion. ]
I G. Turn off the pool flow and temperature recorders.
H. Secure power to P508 A/B.
V.3 Partif Pool Filling Procedures (Pool at Refuel Level or Above)
V.3.1 To increase the water level in the pool with demineralized water from T301 or T300, one of the two following procedures can be used; however, all water in T301 should be used first.
Filling may be accomplished with the skimmer system (Section I A.
VII.5.3) with or without the skimmer pump operating and the ]
reactor either operating or shutdown. Required operational pool makeup will be accomplished in this manner:
- 1. Check capacities of tanks T300 and T301 and check proper valve lineup.
- 2. Observe the pool level and check that the skimmer pump is secured.
Rev.5L0,2/89 App'd JfDm/\ 50P/V-3 I i
_- 1
- 3. Remotely open valve 565B from the primary / pool drain collection system control panel. Insure valve does indicate open.
- 4. The skimmer pump may be started at this point. However, it will fill by gravity if desired.
- 5. When proper pool level is obtained, secure the skimmer pump and remotely close valve 565B. Insure it does indicate closed.
B. The second approved method of filling the pool is via the 4" line from tank T300/301 to the pool pump suction and discharge line,
- 1. Check capacities of tanks T300 and T301 and check proper valve lineup.
- 2. With the pool system in the normal shutdown mode, fill-ing the pool through a pool pump can be avoided by oponing valve V522C and permitting T301 or T300 to drain by gravity feed alone.
- 3. Close valve V522C when the filling operation is com-pleted.
V.4 . Pool Lowering Procedure V.4.1 Lowering P.ool Water Level to Refuel Bridge Two methods of lowering pool level may oe used:
A. By use of the skimmer systein (SOP /VII.5.2). ]
B. By use of the pool pumps P508A or P508B as outlined below.
V.4.2 Before a lowering of the pool level using P508A/B is commenced, Ii place pool system in service as follows:
I A. Isolate one pool heat exchanger utilizing the local inlet gate valve.
B. Place master switch in 1S1 to test.
C. Place V509 to manual /open.
D. Start P508A or 508B.
Rev. 5/02/89 App'd h 5 SOP /V-4 i
- I .
E. Pool lowering procedure is as follows:
NOTE: A visual observation of the in-pool facilities ]
must be maintained while a pool pump is on and during the draining operation. . Specific control over hazards and a radiation survey must be maintained during the course of the draining operation. The pool level will not be lowered below the intermediate refuel level without the specific approval of the Reactor' Manager.
I-
- 1. Health Physics personnel shall be present while lowering pool level to insure that a high activity sample or component is not uncovered causing excessive personnel exposure.
- 2. Check pool area to insure all samples, spacers, and other radioactive materials are low enough to guarantee adequate shielding.
Turn skimmer pump P532 off.
I 3.
- 4. Insure that T301 is valved in service.
- 5. Open manual valve VS22C in room 114 to full open. Note the reduction of flow as the valve is opened.
- 6. With V522C full open, slowly throttle down on the un-isolated heat exchanger inlet gate valve until the flow indicated by the flow recorder in the control room shows approximately 200 gpm. q
- 7. When the pool level is at the desired level or a T301 4 high level alarm is received, secure P508 and immedi-ately close V522C.
- 8. Reopen the inlet valves of both heat exchangers.
- 9. Insure that Health Physics clears the bridge area for ,
I L access.
i l V.5 Pool Cleanup System l l V.5.1 To put the pool cleanup system into normal operation, the following procedure is used: J A. Check valve V515T, V515N and V515P open.
Rev. 5/02/89 App'd hjW S0P/V-5 L
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l B. Check valves V515M, V515X (P513B bypass) and V515Q closed for normal operation.
NOTE: .0pening V515M and closing V515T bypasses flow around i valve V509, HUT-504 and P508A/B to the input of g P5138. Opening V515Q and closing V515P returns 5 processed water to the suction side of P508A/B rather than'back to the top side-of the pool.
C. Make certain that one of three possible demineralized units l' is valved into the cleanup system according to the pro-cedures described in Section VII. ]
- 0. Turn on demineralized flow recorder. Time and date the strip char:..
E. Turn on P5138 from the control room by turning the P513B ,
control switch to the ON position. I I
F. Verify a 50 5 gpm flow rate on the pool cleanup loop flow recorder.
G. Indicated flow rate should be 50 5 gpm and the indicated water purity should be less than 2.0 tahos/cm from the demineralized.
V.5.2 Discharging Excess Water from Primary or Pool System with T301 Full - moved to SMP-20.
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Rev. 5/02/89 App'd M SOP /V-6 I
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SECTION VI SECONDARY COOLING SYSTEM I VI.1 Ctartup of the Secondary System A. Before ' attempting to start up the secondary system, it should be determined that:
- 1. Water level in the cooling tower basin is between 5 and 14 inches. ]
- 2. All personnel are clear of cooling tower equipment and fans. l
- 3. Oil level in the gear reducers to the fans is normal.
j I 4. The automatic sump makeur water isolation valve h electrical power switch is in auto. ]
B. The following manually operated valves in the cooling tower should be in positions indicated:
I Open Closed S-17 S-9 S-113 S-129 S-18 S-10 S-105 S-128 S-101 I S-19 S-20 S-11 S-12 S-106 S-107 S-126 S-21 S-118 S-108 S-121 S-22 S-119 S-109 S-123 S-155 S-120 S-110 S-125
]'
S-5 S-117 S-111 S-127 S-6 S-114 S-112 l S-7 S-8 S-115 S-116 S-102 S-163 J I C. The following valves in equipment room 114 passageway and i
)
waste tank room should be in the positions indicated- i I )
Open Closed S-152 S-151 S-103 S-169 l S-153 S-150 S-160 S-170 S-104 S-159 l Rev. 5/02/89 App'd_b\ SOP /VI-1 l
)'
{
i D. The following valves in equipment room 114 should be in the o position indicated:
l I L Open Closed S-161 S-26 S-132 S-144 S-162 S-41 S-133 S-145 S-131 S-43 S-27 S-154 S-130 S-34 S-28 S-134 S-23 S-35 S-29 S-135 g
S-24 S-45 S-137 S-136 m
? 25 S-140 S-138 S-39 S-141 S-139 S-30 S-142 S-157 S-31 S-143 S-158 E. For operation of the chiller units with feed water from P-1, ].
P-2, P-3, or P-4, the following valves in room 278 should ]
be in the positions indicated as follows:
Open Closed S-53 S-55 S-51 S-148 S-54 S 56 S-52 S-145 S-57 S-58 S-147 S-149 F. Verfy that the Bailey Meter recorder Model E101 in the reac-tor control room is on to monitor secondary flow and temp-
]
]
l" erature during operation. Time and date chart. Secondary outlet temperature for each heat exchanger can be monitored in the control room with the digital readout and selector switch.
G. Verify that the circuit breakers for P-1, P-2, P-3 and ] g 3
P-4 on MCC-2 in the cooling tower are closed and that the ] M control switch on the pannels is in auto, made.
I Rev. 5/02/89 App'd MM _ _ SOP /VI-2 1
H. Start two sacondary pumps for 10 MW operation.
CAUTION: Two pumps cannot be started at the same time because the basin level will be drawn down faster than the makeup water can be supplied, which will result in the actuation of a low sump level trip.
j I After one pump is started, it is necessary to wait from 5 to 10 minutes before starting the second ]
pump.
Verify that the correct flow occurs and that the pumps operate normally. Verify that the automat. c isump makeup water isolation valve has opened. The valve is designed to operate automatically with its control function being: P1, P2 or P3 operating -- the valve is open. When all the P-pumps are secured, with the exception of P4, the valve is closed. The secondary system is now fully operational.
NOTE: The pumps should be operated alternately with neither carrying a major share of total on-line time.
l
- 1. Place the Calgon water treatment units in automatic control locally.
J. Pumps P-1, P-2, P-3 and P-4 may be operated locally during ]
maintenance by means of controls provided at each of the ]
pump stations.
K. Periodically check and adjust valves S-17, S-18, S-19, S-20, S-21 and S-22 located atop the cooling tower to assure equal flow through each.
VI.2 Procedure for Operation of Bypass Control Valves S-1 and S-2 The controllers for operating the control valves S-1 and S-2 are located on the instrument cubicle in the control room as an integral part of the primary and pool water temperature recorders respectively. Provisions are made for both manual and auto-matic control operation modes:
Rev. 5/02/89 App'd (A M SOP /VI-3
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A. Manual Operation
- 1. Energize process system and controller.
- 2. Adjust the valve position with the nanual control button on front panel until pool and reactor coolant tempera- h.
tures stabilize at the desired values.
B. Manual to Automatic Transfer Control can be transferred from manual to automatic opera-tion at any time.
- 1. Turn control transfer switch on front panel to auto position. g C. Automatic to Manual Transfer s NOTE: Caution must be used in going from the automatic mode to the manual mode. If the indicated valve ]
deviation is not brought into balance with the valve adjustment button on the controller prior to turning to the manual mode, and if there is a large difference between the manual position demand and the position of the valve in the stabilizer auto mode, a significant positive or negative reactivity change could occur. This would be due to the valve leaving its position in E
the auto mode and traveling as rapidly as possible B >
to the position demanded by the manual setpoint when the manual mode is selected.
The bal mode permits the manual control posi-tion demand to be equated to the stable position of the valve while being operated in the auto l
mode before the manual mode is selected.
- 1. Turn control transfer switch on front panel to bal position.
- 2. Adjust manual control on front panel until deviation meter on front panel indicates no deviation. With no deviation present, red meter pointer is aligned with red index line of setpoint tape indicator.
- 3. Turn control transfer switch on front of panel to man position. The system temperature is now controlled by manual control.
Rev. 5/02/89 App'd {MttfV\ S0P/VI-4 I
VI.3 Cooling Tower Operations VI.3.1 Operation of The Cooling Tower Fans The cooling tower fans required for operation is a function of both the reactor power level and/or climatic conditions.
Control over the use of these fans rests with the Shift Supervisor who will maintain process coolant temperatures within standard operational limits as specified in the MURR Technical Specifications and Section I of the Standard
, I Operating Procedures.
The oil level in each fan shall be checked as part of ]
each Fullpower Startup Checksheet. After an idle period ]
during the winter months, the blades shall be checked to make certain ice accumuinion on the surface of the blades will not cause an imbalance while the fans are in operation. Such an imbalance could result in damage to the fan units. A vibration switch installed near the gear reducer will stop the fan if excess vibration occurs, but this switch shall not be relied I upon to prevent damage from ice accumulation.
VI.3.2 Deicing The Cooling Tower CAUTION: PLASTIC FILL MUST NjT,BE ALLOWED TO ICE UP.
I During very cold months, the external wooden louvers may become mostly covered with ice. The following procedure should be used:
I A. Notify the Shift Supervisor of the need to deice.
B. Maintain communication either with radios or the intercom box at the cooling tower.
C. Have the control room operator secure the cooling tower fan for the tower Say in which deicing is desired. All three cooling tower bays may be deiced at the same time but it must be remembered that some cooling capacity is lost when deicing.
I Rev. 5/02/89 App'd 4}DM S0P/VI-5
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D. Allow enough time for the fan motor to coast to a stop and j then place the fan motor main breaker forward / reverse switch )'
to reverse.
E. Notify the control room to start the fan. It will now be ;
running in reverse to force heat out through the ice covered slats. ,
-F. Periodically check to see if ice is clear. When clear, use ]
the above procedure to place the fan in forward rotation. ]
l VI.3.3 Winter Operations (Temperatures Expected Below Freezing)
Due to the potential for ice to significantly damage the plastic fill, every precaution must be exercised to prevent ice buildup on the wooden louvers and in the plastic fill.
When the cooling tower is to be left unattended for more than one day (or on a long maintenance day), perform the following steps to prevent ice buildup in the plastic fill:
- 1. Open or verify open the basin steam supply valve.
- 2. Verify the steam solenoid valve operable.
- 3. Secure CT makeup automatic valve. ]
- 4. Prop open CT basin float valve to drain water between auto-matic valve and float valve.
- 6. Secure air conditioning unit and tag. ]
- 7. Secure P-4 and tag.
VI.4 Shutdown of the Secondary System Upon completion of shutdown of the reactor, reactor primary and pool loop cooling systems, the secondary cooling loop can be shut-shutdown as follows:
A. Shutdown secondary pump or pumps. If more than one secondary pump is operating, they should be secured simultaneously to minimize check valve slam. This is done from the control room E e
instrument panel .
Rev. 5/02/89 App'd (d M SOP /VI-6 l
p B. Verify that system flow recorder indicates no flow and.that I the chiller pump, P-4, has automatically started to provide coolant flow to the chiller unit. During winter months when
]
]
the air conditioning units will not be in service, P-4 will ]
be placed out of commission and verification of its operation during these months will not be necessary.
C. Turn off cooling tower fans.
VI.5 Draining and Filling the Secondary System Heat Exchanger and Piping This section has been moved to SMP-21.
VI.6 Secondary Water Treatment Procedures
.I VI.6.1 Secondary Water System Responsibility The responsibility of the secondary water treatment is within the operations group of the reactor, with two individuals given ]
prime responsibility to learn and be closely associated with the ]
total operation. The secondary water treatment system is de-signed to minimize corrosion, deposition, microbiological growth, I and other major chemical problems which are present in the sec-ondary cooling water system.
VI.6.2 Secondary Water Conductivity Control To control conductivity (total dissolved solids), water is sampled and monitored by the conductivity unit located in the tunnel of room 114. If the conductivity is greater than the system setpoint, an automatic blowdown is initiated. The fresh water makeup, which replaces the water lost through the blow-down, lowers the conductivity. ]
I I Rev. 5/02/89 App'd M SOP /VI-7
E VI.6.3 Secondary Water pH Control To control pH, water is sampled and monitored by the pH unit located in the tunnel entrance of room 114. If pH increases above the system setpoint, the acid injection ..ves automatica1- '
ly open and acid is gravity fed into the tower sump. The acid used is concentrated sulfuric acid supplied from the 250-gallon day tank in the cooling tower. ]
VI.6.4 Sample Paths for pH and Conductivity A. During normal operation of the secondary sy. stem, the , auto-matic pH and conductivity control units receive their sample water through valves S104 and S151.
B. During operation of the secondary system with the air condi-tioning units secured and isolated, close S104 and open S103.
This provides a representative sample for these units to control pH and conductivity. To shift the automatic blow-down system during operation with the air conditioning units isolated, close S102 and $101.
C. The pH and conductivity units shut down when secondary ] g pumps (P-1, P-2, and P-3) are secured. ] E VI.6.5 Secondary Water Corrosion Prevention A. The prevention of corrosion in the secondary system is accomplished by automatic addition of a corrosion inhibiter.
B. These chemicals are fed automatically by a metering pump system based on makeup flow.
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i VI.6.6 Secondary Silt, Algae and Mud Control Silt and mud buildup is controlled by the feeding of a chemical silt dispersant to the cooling tower basin. The dispersant is added to ensure solids remain suspended a sufficient amount of I time to allow the secondary blowdown to remove them from the system. This reduces secondary conductivity and minimizes the buildup of silt in low flow are6s, a fouling condition.
addition of two microbiocides/algaecides. The addition fre- ]
quency is determined by weather conditions and reactor oper-ations.
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I Rev. 5/02/B9 App'd (fM SOP /VI- 9
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THIS PAGE INTENTIONALLY' LEFT BLANK i
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Rev. 5/02/89 App'd th SOP /VI-10 ]
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SECTION VII r AUXILIARY SYSTEMS j
VII.1 Reactor power Calculator l'
The. automatic power calculator uses an input signal from the l primary and pool AT summers and calculates a power heat balance using analog type computer circuitry. The power level is read out continuously on a digital meter which gives the reactor power i
in megawatts. The flow signals used to calculate the power are input manually through a. potentiometer built into the. system for both pool and primary flows.
VII.1.1 Setting the Potentiometers The flow potentiometers are set at the fraction of total recorder flow that is being used. The primary flow recorder has a full scale reading of'2000 gpm for each loop, thus the total recorder flow available is 4000. '
To determine the pot setting, add the indicated flow in loops A and B and subtract the cleanup flow from this total. This number is the total core flow. Divide the total core flow by 4000. The resulting fraction should be set into the pot.
The pool flow recorder has a full scale reading of 800 gpm for each loop and the pool cleanup flow is extracted before the pool water flows through the heat exchangers. . To determine the pot setting for pool flow, add the indicated flow of loops A and B and divide by 1600. The resulting fraction should be set into the pot.
Rev. 10/81 App'd (b M SOP /VII-1
1 VII.1.2- Checking Operability of Calculator The accuracy of .the power calculator shall be checked daily after the first set of process data is taken provided steady state tem-perature conditions have been reached. _ This check is made by hand {
calculating the reactor power using the process instrumentation.
The results of this calculation shall be recorded in the comments section of the Process Data log.
VII.2 Ventilation Exhaust' System (EF-13/EF-14)
The ventilation exhaust. system is required to be operable whenever containment integrity is required (Tech. Spec. 4.2.b). Exha'st u fans EF-13 and EF-14 provide the driving force for the exhaust system. The normal exhaust fan lineup consists of EF-14 (the upper fan) running with EF-13 in Standby.
VII.2.1 Fan Failure Alarm Abnormal conditions associated with the exhaust fans are annunci-ated by the Fan Failure Alarm System according to the following diagram.
GREEN YELLOW BUZZER FAN CONDITIONS LIGHT FLASHER One fan running and the other in "AUT0". X One fan running and the other in "0FF" x x of " HAND".
One fan running and no voltage to other X X fan.
No fans running with control power x x available.
One fan running, other in standby, but X X no flow (broken belt, etc.)
Both fans running due to loss of control power.
Both fans running but control power X X available.
Off gas high activity.. X X Rev. 3/12/86 App'd (UQTi\ SOP /VII-2 L- _ _ _ _ _ _ _ _ . _ _ _ _ - _ - _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . _ _ _ _ _ - . _ _ _ _ _ - - _ - _ _ _ _ _ - _ _ - _ _ - _ _ - - - - - - _
VII.3 Emergency Power System VII.3.1 Testing of the Emergency Power System At least once a week the emergency generator will be started automatically and permitted to run for at least 30 minutes.
This event will be noted in the console log. An amber light mounted on a side panel in the control room will energize whenever the emergency generator is running. In addition to this, the emergency generator will be operated for a period of about 30 minutes prior to each startup after a shutdown exceed-ing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Approximately once a month commercial power to the auto transfer switch is interrupted at unit substation B ]
in order to allow the emergency generator to start and immedi- ]
ately assume full load conditions (CP-17).
A modified load test (CP-17) shall precede and a full load ]
test (CP-17) shall follow any work on the emergency generator except for routine maintenance that has been proven to not cause a problem (such as engine oil and filter char.ges, governor oil checks, new fan belts and gas tank sediment draining checks).
VII.3.2 Prior to Starting A. Check engine oil level.
B. Check that fuel pump controls are in auto and on.
VII.3.3 To Start Engine 1.ocally A. Place the Remote-Stop-Run switch to run position.
B. When the engine comes up to speed (1800 rpm), check water flow to drain from engine cooling system.
C. Check fuel settling bowl full of gasoline.
D. Check oil pressure gauge reading properly.
E. Check ammeter reading a low positive charge rate.
Rev. 5/02/89 App'd hf0fA S0P/VII-3 ]
I F. Check that engine temperature does not become excessive
(>212'). If engine temperature does become excessive under a no load condition, this means that the cooling system is not functioning and the engine should be stopped immediately until cooling water can be established to the engine. ]
VII.3.4 To Stop Engine Run engine for 30 minutes and then return Remote-Stop-Run switch to the remote position. Engine will then return to its normal
(!tandby) status.
VII.4 Reactor Demineralized System VII.4.1 Normal Operation Normally there are four mixed resin beds in the system at one ]
time with two beds on line, one in standby or depleted and one in ]
the storage tank for pre-shipment decay. The normal flow path is ]
via a 50 gpm pump, system inlet filters, down through the DI bed, ]
and through system outlet filters. The outlet valve of the sys- ]
tem inlet filter is used as a throttling device with the bypass ]
valve always remaining closed. Although regeneration of a bed ]
is possible, single life pre-generated beds are normally used ]
in this system. If regeneration of DI beds is necessary, the ]
procedures to perform this task are incorporated into SMP-16. ]
l VII.4.1.1 Placing Standby Cleanup Bed on Reactor Service ]
CAUTION must be exercised to prevent a reactor loop low pressure ]
scram from occurring during this procedure! ] '
A. Check the DI RESIN LOG for the status of the affected bed (s). ]
B. INSURE all valves on STANDBY DI column are CLOSED. ]-
C. OPEN valve DI-2 slightly on STANDBY column to allow pressure ] <
to equalize, then open fully. ]
D. OPEN STANDBY column DI-5 to place in parallel with on-line ]
column. ]
l Rev. 5/02/89 App'd \@t(\ 50P/VII-4 ]
E. REMOVE the DEPLETED bed from service by shutting DI-2 and ]
DI-5 on depleted column. ]
F. TRANSFER the DEPLETED bed H3 water to the DCT. (see ]
VII.4.2.7) ]
G. RECORD the transaction in both the DI RESIN LOG ard console ]
log. ]
VII.4.1.2 Placing Standby Cleanup Bed on Pool Service ]
]
A. Check the DI RESIN LOG for the status of the affected bed (s). ]
B. INSURE all valves on STANDBY DI column are CLOSED. ]
C. OPEN STANDBY column DI-1 and DI-4 to place in parallel with ]
on-line column. ]
D. REMOVE the DEPLETED bed from service by shutting D1-1 and ]
DI-4 on depleted column. ]
E. TRANSFER the DEPLETED column H3 water to DCT. (see ]
(VII.4.2.7) ]
F. RECORD the transaction in both the DI Resin log and console ]
log. ]
VII.4.2 Resin Transfers ]
Demineralized water will be used for all resin manipulations. ]
The T-300 flow booster pump should be used any time gravity ]
feed does not supply adequate flow. ]
VII.4.2.1 Resin Loading ]
Te load the resins into the regenerator, first drain most of the ]
excess water from the regenerator to allow an increased educting ]
flow rate, then educt the cation (5 cubic feet), next educt the ]
Rev. 5/02/89 App'd N QTA SOP /VII-5 ]
[
I anion (7 cubic feet). The cation level should be just above the ]
acid header. To properly educt resin into the regenerator, ]
enough water must be added to the resin to create a slurry mix- ]
ture. To educt: ']
A. Insure that all valves are closed on adjacent systems. ]'
B. Connect the quick-disconnect hose to the DI supply and open ]
the T-300 valve RE89. ]
C. Place a barrel under the eductor pipe to contain the resin ]
slurry to be educted. ]
D. Open valves RE7, RE18, at the regeneration station. ]
E. Open REIS, check closed RE16. ]
F. Open vent valve RE9, to allor the regenerator to drain. ]
G. Open RE13, place the resin suction line in the resin and ]
open RE12 to add water to make a slurry. ] ,
H. When water level is sufficient, open R5 to begin eduction. ]
Stir the resin while it is being educted. When water issues ]
from vent valve RE9, close RE13 to allow excess water to ]
drain off. Wait approximately 10-15 minutes. Open RE13 to ]
continue eduction. ]
I. Repeat step H until desired level of resin is obtained. ]
J. When water issues from vent valve RE9, close RE13, then ]
close RE15. ]
NOTE: At this step all resins are covered with water. D0 ]
NOT allow resins to dry out; this can destroy them. ]
K. Close remaining valves, RS, RE12 (inside DI room) and RE7, ]
RE9, RE18, RE89 (at regeneration station). ]
L. Open RE-68 to depressurize the flexible hose, then shut ]
RE-68. ]
M. Record the transaction in both the DI resin log and console ]
l log. ]
Il Rev. 5/02/89 App'd \dM SOP /VII-6 ]
l L____.._____
VII.4.2.2 R-200 Resin Dump ]
A. OBTAIN a RWP. ]
B. Check the DI RESIN LOG for the status of the affected bed (s). ]
C. INSURE that all valves are CLOSED, including unused valves on ]
adjoining system. ]
D. PLACE the resin drying barrel under the dump pipe. ]
E. INSURE the flexible hose is connected to-the DI water supply ]
then open RE-89 and RE-18. ]
F. OPEN RE-25' compressed air isolation valve and SET the ]
regulator to 601rs. ]
G. OPEN RE-10 to pressurize R-200 to 60 lbs. then CLOSE RE-10. ]
H. SLOWLY OPEN RE-11 to dump resin. You nay, at some time ]
i.Jring the dumpir.; need to add water to R-200. Use RE-3 ]
for.this purpose. ]
I. When dumping is complete, CLOSE RE-11, and RE-25, back off ]
on the regulator and vent the air system. ]
l J.
K.
OPEN RE-9 to vent any remaining pressure.
OPEN RE-3 to fill R-200.
]
]
L. When full, CLOSE RE-3, RE-9, RE-18, and RE-89 (T-300 to ]
DI-200 isolation valve). ] ,
M. OPEN RE-68 to vent the pressure in the flexible hose then ]
CLOSE RE-68. ]
N, RECORD the transaction in both the DI resin LOG and console ]
log. ]
- 0. CLOSE OUT the RWP. ]
I VII.4.2.3 Transferring Resin from a DI Column to R-200 ]
A. INSURE that waste tank #2 has the capacity to accept the ]
transfer water. ]
B. Check the DI RESIN LOG for the status of the affected bed (s). ]
l l
Rev. 5/02/89 App'd M SOP /VII-7 ]
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l C. INSURE that all valves, including the ones not being used ]
in adjacent systems are CLOSED.- ]
D.. INSURE the flexible hose is connected to the DI water ]
supply, then OPEN RE-89 and RE-18. ]
E. OPEN the RE-25 compressed air isolation valve and set the ]
regulator to the maximum pressure available. ]
F. PERFORM an H3 water transfer to the DCT if it has not already ]
been done on this bed. (see VII.4.2.7) ]
G. OPEN DI-8, DI-9, and DI-13 and allow the bed to DRAIN for four ]
minutes. ]
H. CLOSE DI-9 and DI-13. ]
!. OPEN DI-7 fully until the sparge begins. You may have to ]
close DI-7. Wait until the pressure in the column vents off 3 and then quickly open DI-7 several times before the hard ]
packed resin breaks loose. When it does, THROTTLE back to ]
the most vigorous sounding sparge and continue for at least ]
ten minutes. If you do ,ng HEAR a good sparge, water may ]
have to be added. ]
J. When completed, CLOSE DI-7 and DI-8. ]
K. OPEN DI-3, DI-6, R-1, RE-7 and RE-16. ]
L. To start the recin transfer, OPEN R-2 and OBSERVE the bulls- ]EE eye for resin mo.wment, fhe DI water booster pump may have ]
to be used for adequate flow. ]
M. After the tr;iisfer is completed, CLOSE R-2, RE-16, RE-7, ]
R-1, DI-3, DI-6, RE-18 and RE-89 (T-300 to DI-200 isolation ]l valve). ]
N. CLOSE RE-25, back off on the air regulator and vent the air ]
system. ]
- 0. OPEN RE-68 to vent the pressure in the flexible hose, then ]
CLOSE RE-68. ]
l i!
Rev. 5/02/89 App'd d# S0P/VII-8 ]
P. RECORD the transaction in both the DI RESIN LOG and the ]
f ,
. console log. ]
VII.4.2.4 Tranfer of Resins from R-200 to Standby DI Column ]
A. INSURE all valves, including unused valves on adjoining ]
systems are CLOSED. ]
B. Check the DI resin log for the status of the affected bed (s). ]
C. INSURE the flexible hose is connected to the DI water supply, ]
then OPEN RE-89 and RE-18. ]
D. OPEN RE-3, DI-13, and "0N THE STANDBY COLUMN" 0 PEN DI-3 ]
and DI-9. ]
E. OPEN R-3 to start the transfer. OBSERVE the resin flow in ]
the bullseye. The DI water booster pump may have to be ]
used to achieve adequate flew. ]
F. When transfer is complete, CLOSE DI-3, )
G. OPEN DI-8 and allow the bed to drain for four minutes, then ]
CLOSE DI-9. ]
H. OPEN RE-25 and SEi the air regulator to 45 lbs. ]
I.
SLOWLY OPEN DI-7 to achieve a 10-15 cfm flow rste or a rate ]
which gives the most vigorous sounding sparge and sparge for ]
at least ten minutes. ]
J. When completed, CLOSE DI-7 and OPEN DI-3 to fill the tank. ]
K. When water overflows through the vent .line, CLOSE DI-3. ]
L. CLOSE DI-13, 01-8, R-3, RE-18, RE-3, RE-25 and back off on ]
the regulator and CLOSE RE-89 (T-300 to DI-200 isolation ]
val ve) . ]
M. OPEN RE-68 to vent the pressure in the flexible hose, then ]
CLOSE RE-68.
]
N. RECORD the transaction in both the DI resin log and the 3 console log. 3 i
Rev. 5/02/89 App'd NM __
SOP /VII-9 ]
VII.4.2.5 Transfer of Resin from DI Column to the Storage Tank ]
A. INSURE that waste tank #2 has the capacity to accept the ]
transfer water. ]
B. Check the DI resin LOG for the status of the effected bed (s). ]
C. INSURE that all valves, including unused valves on adjoining ]
systems are CLOSED. ]
D. INSURE the flexible hose is connected to the DI water supply, ]
then OPEN RE-89 and RE-18. ]
E. OPEN the RE-25 compresseo air isolation valve and set the ]
regulator to the maximum pressure available. ]
F. PERFORM an H3 water transfer to the DCT if it has not already ]
been done on this bed. (see VII.4.2.7) ]
G. OPEN DI-8, DI-9 and DI-13 and allow the bed to drain for four ]
minutes. ]
H. CLOSE DI-9 and DI-13. ]
I. OPEN DI-7 fully until the sparge begins. You may have to ]
close DI-7, wait until the pressure in the: column vents off ]
and then quickly open DI-7 several times before the hard ]
packed resin breaks loose. When it does, THROTTLE back to ]
the most vigorous sounding sparge and continue for at least ]
ten minutes. If you do not HEAR a good sparge, water may ]
have to be added. ]
J. When completed, CLOSC DI-7 and DI-8. ]
K. OPEN DI-3, DI-6, RS-3, RS-5 and DI-13. ]
L. To start the resin transfer, OPEN R-2 and OBSERVE the bulls- ]
eye for resin movement. The DI water booster pump may have ] g to be used for adequate flow. ] E M. After the transfer is completed, CLOSE R-2, DI-13, DI-6, ]
DI-3, RS-3, RS-5, RE-18 and RE-69 (T-300 to DI-200 isolation ]
valve). ]
I I'
Rev. c;/n?/po App'd \M pTI\ SOP /VII-10 ]
l
- i CLOSE RE-25, back off on the air regulator and vent the air ] !
N.
- system. ]
- 0. OPEN RE-68 to vent the pressure in the flexible hose than ]
CLOSE RE-68. ]
I' P. RECORD the transaction in both the DI RESIN LOG and the con- ]
sole log. ]
I VII.4 Transfer of Resin from the Storage Tank to R-200 ]
A. Check the DI RESIN LOG for the status of the affected bed (s). ]
B. INSURE all valves, including unused valves on adjoining ]
systems are CLOSED. ]
C. INSURE the flexible hose is connected to the DI water supply, ]
then OPEN RE-89 and RE-18. ]
D. OPEN the RE-25 compressed air isolation valve and set the ]
regulator to the maximum pressure available. ]
E. OPEN RS-5, RS-1 and 01-13 arid allow the bed to drain for ]
four minutes. ]
I F. CLOSE RS-5 and DI-13. ]
G. OPEN RS-4 slowly to achieve the best sounding sparge and allow ]
it to sparge for ten minutes. ]
H. When completed, CLOSE RS-4 and RS-1. ]
I. OPEN RS-2, RS-7, R-1, RE-7 and RE-6. ]
J. OPEN R-2 to start the transfer. OBSERVE the resin flow in the ]
ballseye. The DI water booster pump may have to be used to ]
achieve adequate flow. ]
When transfer is complete, CLOSE R-2, R-1, RS-2, RS-7, RE-7, I K. 3 i RE-6, RE-18 and RE-89 (T-300 to D1-200 isolation valve). ]
L. CLOSE RE-25, back off on the air regulator and vent the air ]
I system. ]
M. OPEN RE-68 to vent the pressure in the flexible hose, then ]
< CLOSE RE-68. ] j N. RECORD the transaction in both the DI RESIN LOG and the con- ] f sole log. ]
I i Rev. 5/np/go App'd NDM SOP /VII-11 ]
VII.4.2.7 Transferring Tritiated (3 )H Water to the DCT ]
A. Check.the DI RESIN LOG for the status of the affected bed (s). ]
B. ENSURE all valves, including unused valves en adjoining ]
systems are CLOSED. ]
C. ENSURE the operability of the DCT system by pumping down the ]
collection tank prior to this operation. ] '
D. ENSURE the flexible hose is connected to the DI water supply, ]
then OPEN RE-89 and RE-18. ]
E. OPEN DI-9 AND DI-14. ]
F. OPEN DI-10 (DI-200) or DI-11 (DI-201) or DI-12 (DI-202), )
whichever is applicable to this operation, to start the water ]
transfer. ]'
G. When tank is empty, CLOSE DI-10, DI-11 or 01-12 (whichever is ]
applicable) and DI-9. ]
H. OPEN DI-8, R-2 and DI-3 to fill the tank with water. ]
- 1. When full, CLOSE DI-3 and DI-8. ]
J. REPEAT steps D through G so that you have completed two ]
water transfers and fills. The bed will be left in a filled ]
condition. Use CAUTION to assure that you do not overfill ]
the DCT. ]
K. When completed, CLOT' DI-14, R-2, RE-18 and RE-89 (T-300 to ]
DI-200 isolation valve. ]
L. OPEN RE-68 to vent pressure in the flexible hose, then CLOSE ]
RE-68. ] '
M. RECORD the transaction in both the DI RESIN LOG and the ] l console log. ]
~l 11.4.3 Providing DI Water to T300 ] )
DI water may be sent to T300 with or without the use of the ] I1 !
reverse osmosis unit as a DI300 makeup supply. Due to the ]
fact that DCW, after passing through the R.0. Unit, is much ] 4 more pure than raw DCW, the R.0. Unit is normally utilized to ]
prolong the life of the DI300 resin regeneration. However, ] ,
there are provisions for bypassing the R.0. Unit when sending ]
] l' DI300 water directly to DI200 (see VII.4.3.3).
Rev. 5/02/89 App'd dW\ 50P/VII-12 ] l l
~
VII.4.3.1 Providing DI Water to T300 with Reverse Osmosis Makeup ]
Culligan (Polishing) beds are used to augment the R. O. unit. ]
A. Open T-300 supply valve (RE-31). ]
B. - Open R. O. unit discharge valve (R0-10). ]
C. Open inlet valve (RO-11) and outlet valve (R0-12) to ]
Culligan bottles. ]
D. Open DI-5. ]
E. Turn conductivity meter to "0N" and place auto valve switch ]
to "AUT0" (first auto valve should open). ]
F. Push reset button under conductivity meter (second auto ]
valve should open). ]
CAUTION: If valves do not open, the conductivity is at ]
or above alarm setpoint. Place normal / bypass ]
switch to " BYPASS". ] '
G. Place R. O. unit in operate mode and push start / reset ]
button on R. O. unit panel if required to clear alarms. ]
(Pressure should come up to 190-200 psig.) ]
H. Flush R. O. unit through DI-5 until conductivity falls ]
below alarm setpoint. ]
I. Open auto valve isolation valve (DI-17) and shut DI-5. ]
J. Place normal / bypass switch to " NORMAL" if required. ]
TO SECURE SENDING WATER A. Place R. C. unit in " STANDBY." ]
B. Place auto valve switch to "CLOSE." Turn conductivity ]
meter to "0FF" (both auto valves should be closed). ]
C. Shut auto valve isolation valve (DI-17). ]
D. Shut R. O. unit discharge valve (R0-10) and Culligan ]
bottles inlet and outlet valves (R0-11 & R0-12). ]
Rev. ;/op/pg App'd \h M SOP /VII-13 ]
I E. Shut T-300 supply valve (RE-31). ]
CAUTION: The following valves should be left open while ] -
the unit is in STANDBY Mode. ] <
R02 ]
R05 ]
R01 ]
When the unit is not in use, DO N3T TURN OFF - PLACE IN ]
STANDBY ONLY. DO NOT SECURE SUPPLY WATER. ]
NOTE: If for any reason the unit must be turned off or the ]
supply water secured, this condition MUST NOT exist for ]
more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or damage will occur to the filter ]
membranes (see technical manual for details). ]
Normally, the water inlet temperature will r.ot require ]
adjustment and is set at approximately 25 C. Allovi at least 30 minutes of running time to stabilize temperature prior 1 determining if an adjustment is needed. ]
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 ]
]
Transferred .o SMP-22 I VII.4.3.3 Providing DI Water to DI200 Units Using R300 Bed ]
Transferred to SMP-22 ] .
l I
l 1 i Rev. 5/02/89 App'd NBTA SOP /VII-14 ]
, l L___________ _ . . _ _ _ . . _ _ _ _
VII.5 Skimmer System VII,5.1 Normal Startup of the Skimmer System The skimmer system is operated to remove floating debris from the pool at the normal operating level. If necessary, it is also possible to operate this system with the pool at refuel level by securing the skimmer box with valve 548A and recircu- l lating the water with suction taken through valve 548B from approximately one foot below the refuel level.
The skimmer system is put into routine operation according to the following procedure:
A. Verify that no maintenance has been performed on the skimmer .
system since the last shutdown of the system. If mainte-nance has been performed on the system, verify that a system valve lineup checklist has been performed; if not, do so .
before proceeding.
B. Energize pump P532 by turning 0FF-0N switch located on the
~
instrumentation panel in the control room to the ON position.
Vent the pump until it shows a steady discharge pressure.
VII.5.2 Pool Pump Down with the Skimmer System A. Prior to pumping the pool down, insure that there is suf-ficient reserve volume in tank T301 to receive the water.
B. If the pool level is to be lowered below the skimmer suction box, change the suction lineup to the lower suction by closing valve 548A and opening V548B.
C. The skimmer pump discharge normally returns to the pool via valve 515H. Pumping the pool down is accomplished by closing valve 515H and opening valve 524 to redirect the discharge to T301. A single control switch on the drain collection ,
system control board operates valve 515H and valve 524. This switch is normally left in the open position having 515H open and 524 closed. To pump the pool down, flip the switch to Rev. 5/02/89 App'd \dDM SOP /VII-15 ] ~~~
Reset f
I the closed position, applying closing air to valve 515H and opening air to valve 524; then turn on the skimmer cump. When the pool level has been lowered to the desired level, secure the skimmer pump and return the switch to the open position and check to see that valve 515H returns to open, and valve 524 indicates shut.
VII.5.3 Raising Pool Level Curing Operation A. Prior to raising pool level, insure that the isolation valve for T301 is open and there is sufficient water in T301 to raise the pool to the desired level.
B. If T301 has insufficient water, crack open T300 isolation valve and allow T300 water to flow by gravity to T301.
CAUTION: Do not allow T300 water level to drop below 2000 gallons while the reactor is in operation.
C. Pool level is raised by opening va',ve 565B, which valves T301 or T300 (as selected) to the suction of the skimmer pump. The height of T300 or T301 provides sufficient head to overcome the pool head at the pump suction and the pool will gravity fill from the tank. The control switch ]
for valve 565B is on the drain collection system control board in the control room, and is normally left in the closed position. To add water to the pool at a faster rate, start the skimmer pump as per VII.5.1 after valve 565B has been opened. When pool level has increased to the desired level, secure the skimmer pump and shut 565B.
Note that the valve indicates shut.
I Rev. 5/02/89 App'd NN SOP /VII-16 ]
VII.5.4 Replacement of Skimmer Filter 531 The 1 micron skimmer fil 531 will be replaced when the pump discharge pressure exceec. 70 psig. At this point the oP across the filter as indicated by the oP gauge 926 should read greater than 26 psi. The used filter cartridge will be treated as radioactively contaminated material and will be handled and disposed of accordingly.
VII.5.5 Normal Shutdown of the Skimmer System Secure skimmer pump P332 by turning off-on switch on the instru-ment panel to the off position. Normally, there should be no need to change any of the valve settings after shutdown. With P532 off and the local switch locked out, the system can be considered secured.
VII.6 Primary / Pool Drain Collection System VII.6.1 Purpose The primary / pool drain collection system is used to collect t, potentially radioactive water which is near reactor grade (2.0 trihos/cm or less). This water is recycled to the pool system and is never distributed to the building DI water supply. The collection of such effluents substantially reduces activities being discharged via the liqu1d waste collection system.
VII.6.2 System Operation The system may be operated either in automatic or manual.
Normal operation shall be in the automatic mode. The sequence of events in automatic are as followi-Rev. 5/02/89 App'd ldinA SOP /VII-17 ]
Reset
A. The high level sensor detects high level at 2-1/2 feet, or ,
135 gallons, .and the following events occur:
- 1. The pump automatically comes on (the " pump on" light indicates the pump is running).
- 2. The pump discharge valve 565A opens (ensure the "open". ]
light indicates the valve open).
- 3. The high level light indicates high level in the tank.
- 4. The high level alarm sounds. The alarm will clear as q soon as the level recedes below the sensor. The high '
level alarm cutout may be employed if the high level is to exist for some time.
B. After the system pumps below the low level sensor, the .j following events occur:
- 1. The pump stops (ensure " pump off" light comes on). ]
- 2. The pump discharge valve 565A closes (ensure valve ]
indicates closed). i If it is desired to pump the collection tank before the level has risen to the high level sensor, the high level alarm can be simulated by depressing the auto / manual switch. This switch causes the control circuit to.see a dummy high level -
signal which will cause the pump to start and the discharge i valve to open. The tank will be pumped to the low level sensor which will cause it to stop as in auto control.
If for any reason it is desired to secure pumping of the {
collection tank before the low level sensor is reached, depress the manual override switch. This switch simulates a low level to the control circuit. The pump will stop and the discharge valve will close.
NOTE: When the collection system operates, an increase in pool DI water flow should be noted.
I Rev. 5/02/89 App'd M_ S0P/VII-18 ] l
I !
- VII.6.3 System Startup-The primary / pool drain collection system should be in operatio'n any time evolutions involving operation of reactor or pool water systems t re being ' performed. The following steps will prepare ]
the system for operation: '
A. Turn on the panel control power located behind the l instrument cubical.
B. Piace the valve operating system (air /N 2 ) in service as per g Section VII.9.3. ]
E -: C. Verify that the pool level is sufficiently below the over-flow so that water from the collection tank will not over-flow the pool when pumped.
VII.6.4 System Shutdown After all systems have been secured and the building shutdown check is in progress:
A. Verify that the level of the pool is low enough to accept water for the collection tank. If the pool level must be lowerad, do so in accordance with Section VII.5.2. ]
B. Manually pump the water in the collection tank to its low level cutout as per Section VII.6.2. ]
I. C. Secure the valve operating system as per Section VII.9.4. ]
D. Secure the electrical power to the control power panel by opening the switch behind the instrument panel .
I VII.7 Primary and pool Sample Station VII.7.1 Sampling Frequency l l
I- Both the primary and pool influent waters are sampled on a weekly basis, and an activation analysis is conducted by the laboratory section for evidence of fission products and any activation products.
l Rev. 5/02/89 App'd \M ttr(\. S0P/VII-19 ] I
i 'l 9
- - '\
'VII.7.2 pbtaining a Sample Samples may be obtained as described below. Under normal ]
conditions, Health Physics coverage should not be necessary to f ' draw a sample. High activity in the primary or pool system could, however, present a radiation hazard for this evolution.
l A' chirper is mounted ort the hood to indicate a radiation hazard.
A. Turn on hood vent fan and chirper.
B Check all sample valves closed.
Open the appropriate pool or primary sample valve and C.
verify flow by checking the flow indication bubble.
D. After' purging for greater than 30 seconds,, obtain a 500 al ]
sample in a clean poly bottle from the sample discharge valve.
E. After drawing sample, rinse the outside of the bottle with ] -
DI water and make appropriate entries in the primary / pool 'g sample sheet. W F. Check all sample valves closed, and secure the fume hood fan _
and' chirper.
I G. Log the event in the Operations Log Book.
VII.8 Liquid Waste Disposal System i
VII.8d Description A. All drains for potentially contaminated liquids are deliv- j e.ed to the !! quid waste retention system (hereafter refer- j red to as the Waste Tanks - WT) in the below grade area of )
the laboratory portion of the building. The liquid is pumped to the tfi from two waste collection sumps provided for collection of potentially radioactive liquids.
I:
Rev. 5/02/89 App'd bjiWy\ _
SOP /Vil-20 ] i n
1
. i.
I B. The WT system consists of two collection sumps, two sumps, two sump pumps in each sump, one "Y" strainer, three waste ]
tanks, two waste tank pumps, a filter bank and associated ]
piping, valves and fittings.
I C. Each WT has valved drains which connect via a comr'on suction header to the waste tank pumps. This header also has con-nections for chemical addition, DCW, and 1.P air.
D .. The waste pumps should always discharge through the Cuno filters to any waste tank or to the sanitary sewer system. ]
The discharge header has a pressure gauge on both sides of the filter, a sample line, a bullseye, and a low pressure pump cutout switch (set at 5 psig). The low discharge ]
pressure cutout switch automatically shuts off the running ]
pump upon low discharge pressure. ]
E. Each tank has a sight glass for level readings. An air
.g 5 spare line is installed along the entire length of WT1 and
- 2. Each tank has an unvalved vent to atmosphere. WTl or WT3 can receive waste directly from the hot waste sumps, depending on the valve line up. Both tanks have sludge settlement standpipes, but the normal sump discharge is to WT3. WT2 receives eff'iuent directly from the DI200 regen-eration system.
VII.8.2 Dry Active Waste We must make every effort to remove as much waste as possible in the form of dry active waste. We have three methods: ]
(1) Sludge Settlement (2) Cuno Filters (3) Chemical Precipitant Treatment I
I Rev. 5/02/89 App'd {M SOP /VII-21 ]
1 I
A. Sludge Settlement WT1 and WT3 are fitted wich gravity drains to WT2 through E
18" standpipes. This will allow WT1 or WT3 to act as E settling tanks. When the sludge buildup warrants, the sludge is dumped via a 3" drain line at the north end of WT3 or the south end of WT1 into barrels or drying troughs. ]
This sludge is dried and removed as dry active waste.
B. Cuno Filters l
The waste water will normally be pumped through a waste ]
system filter bank. When the LP is high across them, they ]
are replaced with new filters, and the old ones are disposed of as dry active waste. See Section VII.8.11.
C. Chemical Precipitant Treatment Radioactive particulate will attach themselves to carriers which can then be readily filtered out of the WT water.
Without these carriers, even the most efficient filters could not remove this radioactive particulate. After filter-ing, the filters are shipped as dry radioactive waste. See Section VII.8.12.
VII.8.3 Dumping Criteria A. The liquid waste is collected and held until an analysis is made to determine that the specific activity of all radioactive isotopes in the waste is less than the limit specified in the Code of Federal Regulations, Titie 10, Part 20 (10 CFR 20) for dumping liquid waste to the sanitary g sewer. In addition to the dumping limit on each isotope, E l'0 CFR 20 also limits the total activity which the Univer-sity can dump to the sanitary sewer to 1 curie per year for carbon-14, 5 curies per year for H-3 (tritium) and 1 curie per year for other radioactive material, excluding C-14 and Rev. 5/02/89 App'd NW SOP /VII-22 ]
llj
!! H-3. MURR is allocated 80% of the University's limit, i.e.
800 millicurie per year for carbon-14, 4 curies per year for H-3 (tritium) and 800 millicuries per year of other radio-active material . This latter limit and a general desire to minimiza the activity dumped to our environment, dictates that the waste be retained as long as possible to permit the activity to decay off prior to discharge. If the 10 CFR 20 limits are not exceeded and the total activity of ;
I radionuclides does not exceed 10 mci of tritium or 2 mci of other nuclides, the Shift Supervisor may authorize thL water to be pumped to the sanitary sewer. Any tank containing water with an activity greater than 10 mci of tritium or ]
2 mci of other nuclides will be discharged only with the ]
I approval of the Reactor Manager.
B. When the liquid waste exceeds the limits of 10 CFR 20 for dumping, one of two methods will usually be utilized to dispose of the waste. The most desirable option is to retain the water until the activity has decayed off to per-mit dumping. The second option is to chemically treat the ,
waste with a carrier solution that causes the radionuclides to precipitate which facilitates them being filtered out (refer to Section VII.8.12). Precipitates will then be re-moved either by pumping from one tank to another or recir- ]
culating the tank through the WT filters. As the filtering ] ]
I process proceeds, it may be necessary to change the filters l to a smaller mesh size and continue the filtration until the desired activity reduction is achieved.
C. It shall be standard procedure to hold all liquid waste as long as practical to minimize the total actis;ity released.
A sample of the tank is taken and delivered to Reactor ]
Chemistry Group. Results of the analysis are recorded on ]
the Waste Tank Sample Form and the form is sent to the I
Rev. 5/02/89 App'd ldhfA SOP /VII-23 ]
. Shift Supervisor. The Shift Supervisor reviews the sample results and makes the decision of what to do with the tank.
If the Shift Supervisor decides to dump the tank, he sends l the form to Health Physics for their concurrence. If Health Physics concurs that the tank can be dumped, the tank is pumped to the sanitary sewer as per Section VII.8.7. After ]
the operator has completed pumping the tank, he enters the final volume pumped on the sample form and sends the form to Health Physics Department. q D. If the analysis of WT2 exceeds the 10 CFR limits or if the W Shift Supervisor wishes to hold the tank for further decay, WT2 can be pumped to WT1 via the filters, utilizing a vig-orous air sparge. Then WT1 shall be sampled at a later date and re-evaluated to determine where it should be dumped.
E. It may be necessary at some time to discharge a tank of water with activity above 10 CFR limits to the sanitary sewer ]
by dilution of the waste. This wi'll be used only in extreme ]
need and will be performed by special procedure approved by ]
by the Reactor Manager. ]
VII.8.4 Draining WT1 to WT2 ] f When WT1 is nearly full, drain it- to WT2 via the standpipe if ]
being used for sludge collection or bottom drain if not. ]
A. Check valves W1A, 1B, 2A, 2B, 3A, 3B, 7, 9, 23, 38 shut. ]
B. 0 pen W1A if draining via standpipe or W1B if draining via ]
the bottom drain and W2B to commence draining. ]
C. When WT1 is drained to the level of the standpipe or is ] l empty, shut W2B and either W1A or W1B. ]
D. Record the evolution in the Reactor Log. ]
Rev. 5/02/89 App'd idDM\ S0P/VII-24 ]
l
I VII.8.5 Draining WT3 to WT2 When WT3 is nearly full, drain it to WT2 via the standpipe. .]
A. Check valves W1A, 1B, 2A, 2B, 3A, 38, 7, 9, 23, 38 shut. ]
, B. Open valves W3A and W2B to start WT3 draining to WT2. ]
C. When WT3 is drained down to the level of the standpipe, ]
shut W3A and W28. ]
D. Record the evolution in the Reactor Log. ]
VII.8.6 Recirculating and Sampling of Waste Tanks NOTE 1: Notify Reactor Chemistry group before obtaining a ]
sampie. ]
NOTE 2: Always pump through the filters by opening valves W16 ]
and W18, ensuring W5 is closed. Before recirculating ]
any tank, check the following valves closed: W1A, 1B, ]
2A, 2B, 3A, 3B, 5, 7, 8, 9, 22, 23, 24, 25, 26, 27, 38, ]
WD1, WD2, WD3, WD4, WDS. ]
If WP2 is used instead of WP1, open W7 and W8 ]
instead of W9. ]
A. Sampling WT2
- 1. Open W2A, 2B, 9, 16, 18, 24. ]
- 2. Start waste pump (WP1) and verify flow through the bullseye.
p 3. Commence a vigorous air sparge through W2C. ]
as 4. Recirculate for 10 minutes prior to sampling.
- 5. Draw off a sample through W22 and discard to liquid waste drain.
- 6. Draw off a second sample tnrough 'W22 for analysis.
- 7. Shut W22 and secure the waste pump.
- 8. Close W2A, 2B, 9,16,18, 24. ]
- 9. Deliver the sample and completed sample form to the ]
Reactor Chemistry Group for analysis. ]
l
- 10. Record taking of sample in the Reactor Log. ]
l Rev. 5/02/89 App'd \N(HA SOP /VII-25 ]
l
] i I
B. Sampling WT1 ]
l
- 1. Open W1A, 1B, 9, 16, 18, 26. ] j
- 2. Start the waste pump (WP1) anu verify flow through the ] E bullseye. ] E
- 3. Recirculate for 10 minutes prior to sapling. ] ,
- 4. Draw off a sample through W22 and discard to liquid ]
waste drain. ] ,
- 5. Draw off a sample through W22 for analysis. ]
- 6. Close W22 and secure the waste pump. ]
- 7. Close W1A,1B, 9,16,18, 26. ] ,
- 8. Deliver the sample and completed form to the Reactor ]
Chemistry Group for analysis. ]
- 9. Record taking of sample in the Reactor Log. ]
VII.8.7 Pumping to Sanitary Sewer ]
NOTE: Can be done only with Shift Supervisor's or Reactor ] -
Manager's authorization. Check the following valves ]
closed: W1A, IB, 2A, 2B, 3A, 3B, 5, 22, 23, 24, 25, 26, ]
27, 38. If pumping with WP2, open W7 and 8 instead of W9. ]
A. Pumping WT1 to Sewer ] -
- 1. Open W1B, 9, 16, 10, WDI, WD2. ]
2.
3.
Commence a vigorous air sparge through W1C.
Start the waste pump (WP1) and verify flow through the
]
]
l bullseye. ]
- 4. Check waste tank periodically until tank is empty. When ]
empty, secure waste pump. ]
- 5. Shut W1B, IC, 9, 16, 18, WDI, WD2. ]
- 6. Record the volume pumped on the Waste Tank Sample Form ]
and return it to Health Physics Office. ]
- 7. Record the pumping evolution in the Reactor Log. ]
I I
Rev. 5/02/89 App'd d(My\ SOP /VII-26 ]
i
i.., 4 q B. Pumping WT2 to. Sewer. ]
- 1. Open W2B, 9, 16, 18, WD1, WD2. ]
- 2. Commence a vigorous air sparge through W2C. ] ]
- 3. Start the waste pump (WP1) and verify flow through the ] I bullseye. ]
- 4. Check waste tank periodically until tank is empty. When ] !
1 l g empty, secure waste pump. ]
E 5. Shut W2B, 20, 9, 16, 18, k01, WD2. -]
- 6. Record the volume pumped on the Waste Tank Sample Form ]
i and return it to Health Physics Office. ]
- 7. Record the pumping evolution in the Reactor Log. ]
I VII.8.8 PUMPING WASTE MSTEM TO SECONDARY SYSTEM (MOVED TO StiP-15) ]
VII.8.9 Pumping Waste from One Waste Tank to Another ]
A. Puraping WT 2 to WT3
- 1. Check closed valves W1A,1B, 2A, 2B, 3A, 3B, 5, 23, 24, ]
25, 26, 38. ]
- 2. Check WT3 to insure that it has enough room to accept ]
tne volume of WT2. ]
- 3. Open W2A to pump via the standpipe or W2B to pump the ]
entire contents of the waste tank. Open W9, 16, 18, 27. ]
- 4. Start the waste pump (WP1) and verify flow through the bull seye. !
- 5. Commence a vigorous air sparge through W2C. (Except if ]
via standpipe). ]
- 6. When the waste tank is empty, shut W2C, 9, 16, 18, 27. ]
- 7. Record the pumping evolution in the Reactor Log and on the analysis form if there is one.
l B. Pumping Waste Tank 2 to Waste Tank 1
- 1. Check closed valves W1A,1B, 2A, 2B, 3A, 3B, 5, 23, 24, ]
25, 27, 38. ]
- 2. Check WT1 to insure that it has enough room to accept ]
]
I 3.
the volume of WT2.
Open W2A if pumping via the standpipe or W2B to pump ]
the entire contents of WT2. Open W9, 16, 18, 26. ]
Rev. 5/02/89 App'd WM ' SOP /VII-27 ]
l l
- 4. Start the waste pump (WP1) and verify flow through the bullseye.
- 5. Commence a vigorous air sparge through W2C (except if ]
via standpipe). ]
- 6. When waste tank is empty, shut W2C, 9, 16, 18, 26. ]
- 7. Record the pumping evolution in the Reactor Log and on the analysis form is there is one.
VII.8.10 Dumping Sludge from a Waste Tank Sludge will be dumped from WT1 through valve W44 (WT2 through sludge plug and WT3 through W40) into barrels or troughs by a ]
procedure approved by the Shift Supervisor. This sludge will be dried and disposed of as Dry Active Waste.
VII.8.11 Changing Waste Tank Filters A. M ain shift supervisor permission. ]
B. Obt.iin new waste filters and a large bucket. ]
C. Wear gloves, lab coat and shoe covers. ]
D. Ensure all normally closed WT valves are closed. ]
E. Place the filter dr:'1 line hoses in the floor drain. Open ]
drain valve 51.and open the vent valve on housing. ]
F. When water quits running, remove filter cannister and place ]
old filters in bucket. ]
G. Replace filters and hardware, reassemble cannister and ]
close valve 51. ]
H. Open DCW valve 38 and valves 9 and 16 to fill and vent ]
filters. Close vent valve. ]
I. Secure valves 9,16 and 38. ]
J. Wash down area, dispose of collected filters in the drying ]
rack. ]
K. Check self on hand and foot monitor. ]
L. Notify Health Physics to survey area. ]
Rev. 5/02/89 App'd \h M SOP /VII-28 ]
l
V11.8.12 Chemical Precipitate . Treatment A. Drain the waste tank to WT2.
B. Lower the waste tank water pH.
- 1. ' Check all valves at R200 closed.
- 2. Line up acid mixing tank valves and close the pump breaker.
- 3. Open R200 valves RE57, RE58, RES and RE70.
- 4. Start acid pump at R200 station and throttle flow with-RE58.
- 5. Add sufficient acid (6 normal) to lower pH to between 5.0 amd 6.0.
- 6. Secure the acid pump and open the breaker.
- 7. Shut valves RES, RE57, RE58 and RE70.
'8. Drain and flush the acid mixing tank.
- 9. Close the acid mixing tank valves.
C. Sparge and recirculate, bypassing the filters, for 30 minutes.
D. Add a special carrier solution which will be provided by the Laboratory Group.
E. Sparge and recirculate, bypassing the filters, for one hour.
F. Raise the pH.
- 1. Open the WT2 manhole cover. 3
- 2. Add sufficient sodium hydroxide to raise the pH to l 11.0-14.0.
CAUTION: It is better to add too much than not enough. j
- 3. Replace the manhole cover. j G. Sparge and recirculate, bypassing the filter, for 30 j minutes.
H. Secure W.T. recirculation and let tank settle for 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Then pump (without air sparge) through stand pipe, from WT2
~
to WT1.
I. WT1 should now be ready to sample.
J. Recirculate WT2 through filter until they no longer foul up.
.Rdv.
5/02/89 App'd hBA S0P/VII-29 ] I Reset
I VII.9 Nitrogen and Valve Operating Air Systems
.VII.9.1 Purpose The primary function of the nitrogen (N2 ) system is to provide pressurized N2 to the pressurizer. The secondary function of the N2 system is to act as a backup to the air in the valve L operating system.
5 VII.9.2 System Startup The air system is in continuous operation and is normally lined up to provide service to all stations. The air to the valve operator header, however, is secured when the reactor is shut -
down so the air valve in rcom 114 must be opened prior to opera-ting any system valves.
The N2 system is operated only while the reactor is in opera-tion. Before the reactor is made operational, light off the Ny g and valve operating system by the following procedure: E A. Verify that the two banks have sufficient pressure for the impending operation. Ideally one of the banks should be full (2000-2200 psig) and the other bank should have more than 250 psig.
p B. Close the switch which energizes the electrical controls for the system.
C. Check closed the cross connect N2 to air valve V0P8.
D. Open the N2 cut out valve V0P15 in room 114, and verify a N2 pressure of 70 5 psig to the valve operator hee. der. ]
E. Close header bleed valve V0P35.
F. Open the air cut out valve V0P31 in room 114 and verify a valve operator header pressure of 100 10 psig.
G. Open the N2 to air cross connect valve V0P8.
The N2 and valve operating systems are now ready for operation.
Rev. 5/02/89 App'd ldh SOP /VII-30 ]
I
pg , _ , - -- - - - - - - - ---
,D.
!/.:
4 .
VII.9.3 System Operation.
iij .The' operation of.the air and N2 systems is fully automatic. The operation of the system is monitored every four hours during plant operation. The only manual evolutions required are 3 changing bottles on a depleted N2 bank and blowing down the dust ]
- 'and oil filter every four hours. 'If moisture'is detected in the air bled from .the filter, .the filter should be blown down until no further traces of moisture are seen. The filter element turns a dark red color when it traps oil. .The filter element shall be changed when more than 75% of its volume has turned
- dark red-in color.
- VII.9.4 System Shutdown After th'e reactor has been secured and no further valve opera-
.tions are anticipated, the air and N systems 2 are shut down as follows: ~
A. Close the N2 to air cross-connect valve V0P8 to reduce N2 consumption.
, B. Close the N2 cut out valve V0P15 in room 114.
, C. . Close air cut out valve V0P31 in room 114.
LD. Open header bleed valve V0P35, bleed to atmospheric pressure, leaving valve open.
E. Secure the N2 control system by opening the electrical switch at the bottle station.
VII.10< - Compressed Air System VII.10.1- System Startup The air systems are in continuous operation and are normally valved to provide service to all stations.
A. Check all air valves not required closed.
B. Insure main air compressor after-cooler water supply operable with the chill water pump running.
'Rev. 5/02/89 ' App'd N% SOP /VII-31 ]
w- - -
7 - - - _ _ - - --__ , - - - - - - - -
m3 y .
i c Q
~
? ,
s /ph 3[;h , C h.[ N _ h . . . .. . _
i ,
$w% ' ^, , : C. JInsure desiccant' type. dryer contains sufficient desiccant pell et's .
- 5<,. /
Wg'*
c.,.; , D. ; Check the tag. log and 'all pieces of equipment .for oper-cability.r Ey! E. . Ap' ply -electrical' power for each compressor by:
<, 5 ,1. Mainiair.compresso;-
- a. Close main breader on MCC3. - !
1
- 4 'b. Place the local switch to " auto"., -(Manual operation
~
should: be used only; for special tests.) ]
Sy ,
> - ' 2.; Emergency air compressor u
' <;. l. , ,-
- a. .Close breaker #3 on the Eniargency Power Panel.
b.-. Close- the~ local switch disconnect at the compressor.
. 2,
- 3. 16" valves y[ l a. -Close breaker #18 on the Emergency Lighting Panel.
- b '. - Close local: toggle switch att the compressor.
.< 4. . ' Instrument - ai r. compressor (Johnson) a.-.Close switch #31 on LP11.
? Jb. Close local' switch at the compressor.
,x
,o 'When' any piece of' equipment is placed in service, monitor the
. . operating equipmentLuntil satisfied that it is operating properly.
.N VII.10.2 ~ System Operation C The' main air compressor operates continuously to supply air to the' facility. The pressure is maintained between 95 to 115 psig The' desiccant dryer has a viewing window' for pellet level in-spection; and the supply should be replenished when the level ifalls below the window. The system requires that the after-cooler be in operation whenever the compressor is in operation.
Should DCW to the building be secured, the main compressor must be secured to prevent damage to the equipment (REP-12). ]
e
'Re'v.'5/02/89 App'd 4)M SOP /VII-32 ]
L
= _ _ - - - _ - _ - _ _ _ _ _ - - - _ - _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - - - - _ - _ _ _ - _ _
The emergency air compressor is always available as a backup for the air system in containment. It is checked for proper operation. weekly. The compressor assumes the load at 65 ! 10 L psig and supplies sufficient air for all door gaskets and equip-ment within the containment. The compressor is electrically p supplied from breaker #3 of the Emergercy Power Panel.
l The backup air compressor for 16B isolation valve will only operate upon failure of both the main and emergency air com-pressors. The compressor assumes the load at 60 5 psig. The compressor provides air only for valve 16B and will allow the valve to be operated as required. The compressor is electrical-ly supplied from breaker 18 of the Emergency Lighting Panel.
The instrument air compressor is always valved for operation and 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.10.3 Shutdown The main air compressor may be shut down for maintenance during operation provided that:
A. Large. volumes of air are not required for a particular evolution.
NOTE: Check need for Topaz Counting System. ]
B. The cross-connect valve to the backup doors (supplied from ]
the emergency compressor) is open to provide an alternate ]
supply of air to keep the backup doors open. ]
l Rev. 5/02/89 App'd MM _ SOP /VII-33 ]
1
- --- 4
~ ~ ~~ ~ ~ ~ ~ - - -
b_ . g -
p[Wy
[ 7- ,
i-
'r
-E' <
~ C.t _.0perability' of the emergency air compresso.rgis checked.'
Should.the_ facility. lose DCW water, the. main air compressor must be shut down as per REP-12. To shut.down the com-. ].
[, , ' pressor, the local' auto /off/ manual switch,is_ turned' to -
of f" ~. The _ compressor may be electrically : isolated by opening the main breaker.on.MCC3.
L - The emergency air compressor must always be operable. !
1 P whenever the reactor is operating. It may.be secured at'its y-' local ' breaker. Breaker #3 on the emergency power panel i L . should not be -secured because it supplies power to the isolation doors, door 101, and the personnel airlock doors.
L With the reactor operating,; the compressor for isola- l tion valve 16B may only be electrically . secured when the valves are placed.in' the closed position. Should this be necessary, open the' local switch only,.because the main switch also provides power to the facility and reactor isolation systems.
The instrument air compressor may be shut down by-opening its' local breaker. 'Its main supply may be secured at breaker #3 of LP11. When secured, if air supply is still ]
required, the cross-connect valve from the main compressor may be. opened.
If'any of the components or compressors above are secured or placed in a position other than normal, the component shall be tagged in accordance with the tag-out procedure,
,s_
t Rev. 5/02/89 App'd Crof\ SOP /VII-34 ]
u___.__ __m______________-___.________m_.m____ _ _ _ _ _ _ . _____m m.________._____- .-___m___m.___ __m____m ___
L i l
1 l
VII.11 Sulphuric Acid System ]
i VZI.11.1 Receiving Bulk Acid 3 CAUTION: This process'is extremely dangerous. Protective ]
equipment must be worn. Always have an available ]
r supply of water and sodium bicarbonate. ]
L
. ulk sulphuric acid is delivered by tank truck and B ] l is transferred to the storage tank by air pressure ] 'I or gravity drain. When possible, the gravity drain ]
method should be used. In the event air pressure ] l 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 exceed 15 psig and closely ]
monitor tank levels. ]
A. Check valve 1 closed and valve 2 open. ]
B. Open valve 3. ]
C. Crack open the Tank-O-Meter bubbler valve 7 to give an air ]
flow of 3-4 bubbles per second. Note and record the tank ]
level indicated on the Tank-0-Meter. Also note the level ]
in the Day Tank. ]
D. Remove the cap on the fill line to enable connection of the ]
transfer line from the truck. Open fill line valve and ]
commence filling the tank. ]
E. While the tank is filling, watch the Tank-0-Meter to insure ]
that an air flow of 3-4 bubbles per second is maintained. ]
CAUTION: If the system is over filled, acid will spill into the ]
Mixing tank. The heat generated at this point could ]
result in damage to the acid handling system. ]
F. When the tank volume reaches 700 gallons, have the driver ]
secure the transfer. ]
G. Have the driver vent the pressure off the truck. ]
Rev. 5/02/89 App'd idDe SOP /VII-35 ]
l H. Disconnect the hose from the truck and allow the acid in the ]
hose to drain into the storage tank. ]
I. Disconnect transfer hose from the storage tank. ]
J. Record the final volume of both storage and day tanks. ]
Report to driver the amount of acid received. Close the ]
bubbler valve. ]
K. Verify that the bubbler valve, valve 1, and valve 3 are ]
closed and valve 2 is open. ]
L. Close fill line valve and recap. ]
M. Log evolution in console log. ]
VII.11.2 Transferring Acid from the Storage Tank to the " Day Tank" ]
When the acid in the day tank has been used, the tank is refilled with acid from the storage tank by carrying out the following procedure:
A. Check valve 2 open and open valve 3. j' B. Crack open the bubbler valve (7) tc give an air flow of 3-4 bubbles per second.
C. Record the volume of acid in each tank.
D. Check valve 1 closed.
E. Screw down on the air regulatory (6) until a pressure of 15 psig is indicated on the pressure gauge.
F. Close valve 2 and open valve 1. The indicated pressure will drop until the storage tank has been pressurized and the actual transfer begins. When the pressure rises above 15 psig, reduce it to 15 psig by adjusting the regulator.
l G. During the transfer, monitor the storage tank and day tank l evel s . Maintain a bubbler flow of 3-4 bubbles per second on the Tank-0-Meter.
H. When the day tank is full, close valves 3 and 1.
I. Open valve 2 to depressurize the storage tank. g J. Back off on the air regult. tor (6). ] B K. Record the final volume of acid in each tank.
L. Close the bubbler valve.
I Rev. 5/02/89 App'd W\ SOP /VII-36 ]
I SECTION VIII REACTOR EXPERIMENTS VIII.1 General Requirements VIII.1.1 Reactor Utilization Request All experiments conducted in the MURR reactor facility must be approved by the Reactor Manager. The mechanism for obtaining this approval and for conducting the required staff and advis-ory committee reviews is outlined below.
A. Reactor Utilization Request Description
.l The approval and review machinery is begun by the prepara-tion of a Reactor Utilization Request (RUR). The RUR is prepared by the experimenter with the assistance of the MURR staff. Instructions are obtained from the Reactor I Manager. The RUR describes the experiment in considerable detail. It also presents the activities (and isotopes) which may be produced and details the methods of handling the radioactive waste. It also lists the Special Nuclear Material and by-product licenses applicable to the experi-ment. The most important part of the RUR and the one which should be given considerable effort in its preparation is the safety analysis. This part of the RUR shall analyze all possible accidents and transients to determine if the experiment involves an unreviewed safety question as de-fined by 10 CFR 50.59. It is important that the experi-menter thoroughly research his experiment in an attempt to resolve all questions which may arise in the review process.
B. Reviews
- 1. The initial review of the experiment is conducted by the MURR staff while they are assisting the experi-menter prepare the '"". Hopefully most of the safety questions will be raised and analyzed during this review.
Rev. 10/81 App'd VM\ SOP /VIII-1
I I
- 2. The RUR is then sent to the Manager of Health Physics (HP) for his review.
- 3. The Manager of Health Physics reviews the RUR to ensure ]
that all necessary radiological control measures will be taken in the proposed experiment. He also checks the applicability and adequacy of the by-product license (s) under which the experiment is to be conducted. However, his review is not limited to the above areas. He may recommend limitations or additional analyses in other g areas. If the Manager HP approves of the experiment, he E will indicate the additional limitations (if any) recom-mended and sign the RUR in the space provided.
- 4. The Reactor Manager will analyze the proposed experiment to determine if it represents a new class of experiment or represents a change to an existing experiment which has safety significance. If either of the above condi-tions apply the Reactor Manager will submit the RUR to tne Reactor Safety Subcommittee (RSSC) for their review. The RSSC conducts the reviews of all new experiments for the j Reactor Advisory Committee (RAC). Their review is pri- I marily directed toward determining if the new experiment t
introduces an unreviewed safety question in accordance 1 with 10 CFR 50.59. If the RSSC finds that the experi-ment does not involve an unreviewed safety questions and recommends approval, the RUR review is completed. The RSSC may, however, refer the experiment to the RAC for its review. This may be done because of unusual hazards, ] ;
special conditions involved or because the RSSC feels that an unreviewed safety question does or may exist.
1 I;
Rev. 5/02/Ro App'd bx5Q SOP /VIII-2 ]
The Reactor Advisory Committee (RAC) will normally review 5.
an experiment only if the experiment has been referred to it by the RSSC. If the RAC determines that the experiment does not involve an unreviewed safety ques-
'I tion the review process is complete.
6 If the RSSC and/or the RAC feel that a proposed experi-ment introduces an ur. reviewed safety question the exper-6 iment must be submitted to the NRC for final review.
The MURR staff will generally prepare the documents necessary for submittal to the NRC.
C. Approval of RUR After all of the reviews have been completed the Reactor Manager will indicate on the RUR any additional limi',ations required beyond those listed in the data package and will then sign the RUR as being approved. Copies of the approved RUR will be distributed to:
- 1. The experimenter
- 2. Manager of Health Physics ]
- 3. Reactor Safety Subcommittee ]
]
- 4. Reactor Advisory Committee (if RAC was involved in the review)
- 5. Reactor Service Engineer ]
D. RUR Review and Update
- 1. Active RUR's will be reviewed by the Reactor Manager ]
I and the Principal Experimenter on an annual basis.
- 2. The Principal Experimenter may use the RUR review to up-I date the experiment description; to request changes to the experiment; to change the list of authorized users on the experiment; and to f amiliarize himself with the limitations placed on the experiment.
- 3. The Reactor Manager will use the RUR review to ensure that the experiment descriptions, activities, isotopes, handling procedures, license considerat'ons and safety analysis are valid for ti,e current range of experiments.
Rev. 5/02/89 App'd U4hrv'\ 50P/VIII-3 ]
VIII.1.2 Flammable or Toxic Materials l t
A. Definitions
- 1. Flashpoint of the liquid shall mean the temperature at I which it gives off vapor sufficient to form an ignitable mixture with the air near the surface of the liquid or f within the encapsulation vessel used. ] )
- 2. Liquid shall 'mean, for the purpose of this section, any material which has a fluidity greater than that of 300 l penetration asphalt when tested in accordance with ASTM Test for Penetration for Bituminous Materials, D-5-65.
- 3. Combustible liquids shall mean any liquid having a flash-point at or above 140*F (60*C).
- 4. Flammable liquids shall mean any liquid having a flash-point below 140*F and having a vapor pressure not exceed- :
I ing 40 pounds per square inch (absolute) at 100*F. ,
- a. Class I liquids shall include those having flash-points below 100 F and may be subdivided,
- b. Class II liquids shall include those having flash-points at or above 100 F and below 140*F.
- c. Class III liquids include all combustible liquids.
- 5. Safety can shall mean an approved container, of not more than 5 gallons capacity, having a spring-closing lid and spout cover and so designated that it will safely relieve internal pressure when subjected to fire exposure.
B. Limitations of Flammable and Combustible Liquids .
- 1. No flammable or combustible liquids may be taken into the containment building unless approved by the Reactor ]
Manager. ] f
- 2. Storage of flammable or combustible liquids in contain-ment is prohibited unless the Reactor Manager has I approved a written request to store the material in the containment building. ;
Il j Rev. 5/02/89 App'd M SOP /VIII-4 ]
l
C. Toxic Materials The materials listed in Appendix B or any material suspected ]
to be toxic, will not be taken irto the containment building ]
unless specifically authorized in writing by the Reactor ]
Manager. ]
l VIII.1.3 Corrosive Chemicals Materials which are chemically incompatible with the reactor I system components from the view pont of corrosion shall be sub-ject to special scrutiny and control. Experimenters are prohib-ited from placing any material in experimental positions (beam-port, thermal column, P-tube, bulk pool, reflector, or flux trap) which have not been listed as to type and amount on an approved RUR.
VIII.2 In-pool Irradiations This section covers the irradiation of samples and any experi-
.l mental measurements in (1) the flux trap, (2', the graphite reflector, (3) the lead shield bulk pool facility and the bulk pool.
VIII.2.1 General Requirements All in-pool irradiations must be under an approved RUR. Section 3.1 of the Technical Specification lists the reactivity limits applicable to in-pool experiments. The Reactor Services I Engineer will coordinate the loading of all in-pool experiments to insure that none of the Tech Spec reactivity limits are violated. An in-pool irradiation loading sheet will be filled ]
l out for each sample (or sample type). The completed sheets will be kept in the control room until the sample is released.
These sheets will enable the operations staff to be continuously informed of the experimental loading of all in-pool facilities.
I Rev. 5/02/89 App'd hihV\ SOP /VIII-5 ]
I
I The loading sheet will also document the reactivity worth of I the sample (s) listed on the sheet (except for bulk pool samples). ]
The Shift Supervisor shall insure that all sample handling evolutions are properly performed and documented. It shall be ]
the responsibility of the shutdown crew to verify that all ]
samples and/or spacers are properly stored and/or accounted for. ]
VIII.2.2 Sample Encapsulation All samples to be irradiated in the reactor pool will be encapsulated in either a seal-welded or crimp sealed aluminum can or a threaded aluminum capsule. Only the seal-welded can will be used in the flux trap.
The seal-welded aluminum cans have been tested to rupture pressures of 400-700 psig, but no sample will be loaded in a seal-welded can which will generate a pressure greater than 100 psig (assuming complete decomposition of the sample).
Where practicable a sample will be doubly encapsulated to minimize the possibility of release of the sample material.
All corrosive materials must be doubly encapsulated. The primary encapsulation may be an aluminum can (seal-welded or threaded) or a sealed quartz vial. The quartz vials have a very low rupture pressure so precautions must be taken to eliminate 5
possible pressure build-up when quartz vials are used. E Sample cans will be weighted if necessary to insure that the sample has negative buoyancy.
VIII.2.3 Flux ' rap Irradiations Since the flux trap region has a positive temperature and void coefficient of reactivity, additional limitations are placed on all samples to be irradiated in the flux trap.
All flux trap samples will be seal-welded, leak checked and will have a negative buoyancy.
I Rev. 5/02/89 App'd hlW\ SOP /VIII-6 ] {
I'
.The flux trap sample holder will be loaded or removed from the reactor only when the reactor is shutdown. The flux trap sample holder must be securely latched in place while it is in the reactor. DO NOT under any circumstances unlatch the flux trap until the. control blades are full in.
For verification that the flux trap is prope-ly latched, an operator other than the operator inserting the ilux trap will visually observe its proper latching.
All flux trap irradiations will be shown on a flux trap loading sheet which must be signed by the Reactor Service ]
Engineer or his designated representative. If the sample ]
loading is unique the Reactor Physicist will check the Service Engineer's calculations of the total reactivity worth and will also sign the loading sheet.
If there are insufficient samples to fully load the flux trap sample holder, the holder will be loaded with aluminum spacers to insure that the samples cannot move during reactor operation. The sample hold-down rod must be securely pinned or wired to the sample holder to satisfy the Technical Specification requirement of a secured experiment. When the loading of each tube in the flux trap is completed, the operator shall verify that the proper sample height loading has been achieved by lift-ing the unloading rod to the mark and observing that the top of-the highest sample is in line with the unloading door.
VIII.2.4 Handling of Irradiated Samples ] ,
(see H.P. SOP-4 for additional clarification)
Every effort shall be made to maximize the decay time before an irradiated sample is removed from the pool. This is done to allow short lived activity to decay. q No radioactive material will be moved in the MURR pool )
which causes a working area dose rate of as much as 100 millirem per hour without the presence of a member of the Health Physics staff who is monitoring the operation. The Health Physics monitor will monitor the operation to minimize radiation exposure to personnel, terminating the operation if necessary. l Rev. 5/02/89 Ap d D3Div\ SOP /VIII-7 ]
____ _ - - - _ - - - - - - - . - _ _ _ _ _ _ J
I Radioactive materials in the MURR pool causing working area dose rates less than 100 millirem per hour may be moved within the pool without the presence of a member of the Health Physics staff if, and only if, a licensed Reactor Operator or qualified sample handler surveys the operation.
VIII.3 Pneumatic Tube (P-tube) System Irradiations VIII.3.1 Limitations on P-tube Use A. No irradiation in the p-tube will be permitted unless it has been authorized by an approved Reactor Utilization Request (RUR).
B. The Reactor Manager will maintain a list of the approved RUR's and the limitations applicable to each RUR. This list will be kept in the control room for use by the Reactor Operator.
C. The Reactor fianager will also maintain a list of the individuals authorized to use the p-tube system and the RUR numbers they are authorized to use. An individual is placed on this list at the request of the principal experimenter for the RUR to be used. The request is made by filling out an " Experiment Utilization Request" form and submitting it to the Reactor Manager via the Manager of Health Physics. This form is used to certify that the experimenter has:
- 1. Satisfactorily completed a checkout on the use of the p-tube system including the applicable emergency procedures; ,
- 2. Received Health Physics indoctrination in those radia- I tion control measures applicable to p-tube irradiations.
A few individual experimenters will be authorized to i conduct p-tube irradiations at other than normal work-ing hours (0800-1700). This authorization will be granted only to those individuals who have considerable Rev. 5/02/89 App'd W&M S0P/VIII-8 ] i Reset i 1
experience in p-tube irradiations and have'shown out-standing knowledge and judgement in the radiation con-trol measures applicable to p-tube irradiations. The i Experiment Utilization Request form is also used to l
initiate a request for these (night time) irradiations.
D. The experimenter shall take the following radiation control measures prior to conducting p-tube irraidations:
- 1. He shall insure that a radiation detector with audible indication is in the laboratory and is operating properly.
l
- 2. He shall wear his film badge and dosimeter during the i rradi ations . If the experimenter is doing a number of irradiations, he shall check his dosimeter period-ically to prevent over exposure.
E. Normally during P-tube irradiations, the experimenter will ]
remain in the laboratory to which a dispatched rabbit will ]
return. ]
When an experimenter does not remain in the laboratory ]
to which a dispatched rabbit will return, the following ]
must be done: ]
- 1. Notify control room of intent to leave laboratory. ]
- 2. Inform control room operator of where the experimenter ]
can be reached (i.e., room and phone number). ]
- 3. Place cart in front of fume hood to which dispatched ]
rabbit will return and post the cart with the following ]
information: 3
- a. Experimenter Name ]
- b. Isotope ]
- c. Amount (mci, pCi) ]
- d. Return Time ]
Rev. 5/02/89 App'd WhY\ SOP /VIII-9 ] . . .
i...-.
VIII.3.2 Sample Limitations A. Any radionuclides having at atonic number from 3 through 83 plus tritium may be produced in the p-tube system. Activity will depend on the sample matrix, time of irradiation, and power level . Prior to the irradiation of a particular sample type, an estimate will be made of the activity produced by the major constituents. Sample activity will be limited to 25 mC1. Flux monitor, container and cadmium shield activity will be limited to 50 mC1. Higher activi-ties must be specifically authorized in the experimenter's RUR.
B. Each sample must be properly encapsulated as follows:
- 1. Solid samples will be wrapped in polyethylene or aluminum foil, sealed in polyethylene tubing or sealed in a polyethylene vial.
- 2. Liquids will be sealed in a polyethylene vial or polyethylene tubing with the ends heat sealed to prevent inadvertent spilling. Liquids cther than water and biological fluids will be double encapsu-lated with the secondary encapsulation being a high density polyethylene rabbit.
- 3. Powder sanoles will be sealed in a polyethylene vial and irradiated in a high density polyethylene rabbit.
Boron and boron compounds in powder form will be sealed {
in high density polyethylene within the rabbit.
- 4. A metal liner such as cadmium sheet may be used in the rabbit providing it is in one piece and covers at least 80 percent of the rabbit's interior surface. The experimenter shall take measures to insure that the heat generated by the metal can be dissipated and will not cause damage to the sample or rabbit.
- 5. The experimenter shall insure that the sample is )
adequately secured in the rabbit (by polyethylene l packing, etc.) so that the motion within the rabbit is minimized. ,
1 Rev. 5/02/89 App'd Wirth SOP /VIII-10 ]
I
3 C. Material which may be irradiated in the p-tube system includes water, plant and animal tissue and fluids, bone, l.
air filters, soils, rocks, soil extracts, coal, paper, meteorites, fibers, dried paint, safe insulation and
~ I~ glass. Pure elements, alloys and compounds not exempted in D below may also be irradiated subject to the activity limitations in A.
D. Unless it is specifically sathorized in the experimenter's
- RUR, the following materials will not be . irradiated in the p-tube system:
l E. 1. Natural uranium;
- 2. Special nuclear materials as defined in Title 10, Part
]
70, Paragraph 70.4m of the Federal Code of Regulations (i.e., plutonium, uranium-233, or uranium enriched in t isotope 233 or 235);
- 3. Pure elements: Li , Na, K, Rb, Cs , Ca, Sr, Ba, Hg, Os ,
H, 0, F, Ne, Ar, Kr. Xe, and P;
- 4. Compounds: NH 4 NO 3 , CaC 2 , Ca0, perchlorate, perman-ganates, Na20 , and Na202;
- 5. Materials which chemically react with water to produce undesirable quantities of heat and pressure;
- 6. Any explosive, flammable, combustible, or toxic materials.
F. Capsules may be run shielded with cadmium or boron (as ]
boron, BC, or BN) but weight and time are restricted due to the heat generated and their reactivity effect on the I reactor. The experimenter shall take measures to insure the heat generated can be dissipated without causing damage to the rabbit or sample. The following limitations apply to shielded capsules in addition to the activity limits of Section VIII.3.2.A:
I Rev. 5/02/89 App'd M SOP /VIII-11 ]
g
- 1. The authorized p-tube user will inform the control room he is going to run sF.91ded capsules and will insert the rabbit so that the cap is on top when the rabbit is in the reactor.
- 2. Cadmium shielded capsules:
- a. 5 or less grams of cadmium may be run for up to 30 minutes.
- b. 50 or less grams of cadmium may be run for up to 10 seconds in row 1 or 20 seconds in row 2.
- 3. Boron shielded capsules:
NOTE: The weight limit is only on the boron, i.e.,
the carbon weight in BC does not count towards the weight limit.
- a. 10 or less grams of boron may be run for up to g 10 seconds in row 1 cr 20 seconds in row 2. m
- b. Between 10 to 15 grams of boron may be run up to 10 seconds in row 1 or 20 seconds in row 2, but must be approved by Director of NAA and Reactor ]
Manager prior to running.
G. Except for the boron or cadmium shielded samples, the con- ]
trolling factor for determining the weight and time limits of a sample to be irradiated in the p-tube is the activity limitation of Section A. If the activity limits do not further restrict a sample's size, the following weight limits shall apply:
E
- 1. For irradiation times up to 30 minutes, the maximum E weight of irradiated materials in one rabbit will be 2 grams with two exceptions:
- a. A maximum of 10 grams of water or dried feces;
- b. Only 1 mg of chemical compounds in solution.
l 2. For irradiation times of 30 minutes to I hour, the maximum weight of irradiated materials in one rabbit l
will be 1 gram with two exceptions:
- a. A maximum of 10 grams of water or dried feces; i
- b. Only 500 pg of chemical compounds in solution.
~
Rev. 5/02/89 App'd OlB(f\ 50P/VIII-12 ] 1 Ili
The weight limits above do not include the weight of the rabbit, polyethylene vial, or packing, or the cadmium (or ether metal) shields.
The maximum irradiation time for most samples will be one hour at power levels 15 MW and 30 minutes for power levels > 5 MW Hair, fibers, paint, air filters and flux monitors may be irradiated for a maximum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at' power levels 15 MW and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at power levels > 5 MW.
The following additional limitations shall apply for irradiations > 10 minutes:
- 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 holes are punched in the top of the poly-thylene vial to relieve prenure.
Deviations from the above weight and time limitations must be specifically authorized in the experimenter's RUR.
VIII.3.3 Rabbit Limitations A. The only type of rabbit which may be used in the p-tube ]
system is the high density rabbit. This type of rabbit will be used for all irradiations (see Section VIII.3.2.B). Each ]
high density rabbit will be limited to six insertions or two hours of total irradiation, whichever occurs first. To account for the irradiation history of high density rabbits, the experimenter will place one mark with a marking pen on the high density rabbit for each insertion up to and including 10 minutes. For irradiations longer than 10 min-utes, a mark will be placed on the rabbit for each 10 min-ute period or fraction thereof. For example, if a rabbit is irradiated for 25 minutes, it will receive 3 marks. When a rabbit has received 6 marks, it will be discarded. Each rabbit must be examined for cracks or other signs of potential failure before it is used.
Rev. 5/02/89 App'd M SOP /VIII-13 ]
I VIII.3.4 Sample Irradiation Procedures VIII.3.4.1. When experimenters have met the requirements of VIII.3.3 and are ready to run their experiment, they shall first make certain that the P-tube system for the desired irradiation position is not in use; i.e., the system "in use light" should be off, then they shall call the reactor control room giving their A. Name B. Laboratory room number C '. Experiment file number D. Project number E. Length of time the sample will be in reflector F. Number of irradiations to be done under A - E VIII.3.4.2 After blowers are verified "0N" by the control room operator, the system will be operated by the following procedure:
(THE POSITION OF ALL CONTROLS AND INDICATIONS ARE SHOWN ON FIGURE VIII-1)
NOTE: THE " RETURN" PUSHBUTTON WILL RETURN RABBIT TO FUME i H000 DURING ANY PORTION OF IRRADIATION CYCLE.
A. Set timer to desired irradiation time.
I
- 1. Depress and hold pushbutton I.
- 2. Depress numbered pushbutton until desired time is indicated on display (HH.MM.SS).
- 3. Release pushbutton I.
- 4. Timer is now set, and need not be touched again until a new irradiation time is required. ;
B. Place power switch to "0N" (" System in use", lamp lights).
C. Depress " Dispatch" pushbutton (system is now lined up to accept rabbit).
D. Insert rabbit, with cap down.
E. Observe " Rabbit in Reactor" lamp lights, and timer starts. I Rev. 5/02/89 App'd dihh SOP /VIII-14 ]
Reset I i
I I
I DISPLAY l
mesess I O O I l I P.B. R AB BIT DISPATCH I
P.B.
RETURN I
ON I SYSTEM IN USE orr I 8 I Figure VIII-1 Control Station for Laboratories I 216, 218, 227, 228 Rev. 5/02/89 App'd M I SOP /VIII-15]
Reset I
F. ' At end of pre-selected time, system will return rabbit to
" catcher" in fume hood.
G. If more then one rabbit is to be run, using same irradiation time, depress " Dispatch" pushbutton and insert next rabbit.
H. After last rabbit is run, place power switch to "0FF".
I. Call control room and give the irradiation time for the rabbit and number of rabbits irradiated. Verify numbers consistent with those reported in section VIII.3.4.1.E and F. If different, determine cause of discrepancy. ]
VIII.3.4.3 After the rabbit has returned from the reactor, check the dose rate.
VIII'.3.5 P-Tube Emergency Procedures
'VIII.3.5.1 The most common occurrences will be trouble with the station i controls, the possibility of the rabbit sticking in the tube, and the rabbit coming apart in the pneumatic tube system.
VIII.3.5.2 Station Control Malfunction A. If the rabbit is in the reactor and is not automatically discharged, press the " return" pushbutton and notify the control room immediately.
B. If the rabbit is not in the reactor and station controls do not work, call the control room. The reactor operator will then get in touch with the electronic technician.
NOTE: THE EXPERIMENTER IS NOT AUTHORIZED TO ATTEMPT REPAIR OF THE SYSTEM.
C. Report to the control room the material contained in the I
sample, the expected activity and dose rate, and the ap-proximate time the rabbit can remain in the reactor without creating any hazard.
D. The reactor operator will get in touch with a health physics technician to monitor as required.
Rev. 5/02/89 App'd {M[XD\ SOP /VIII-16 ]
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 sample, the expected activity and dose rate, and the approximate time the rabbit can remain in the reactor without creating any hazard or melting.
A. After the control room is aware of the problem, press the
" return" pJshbutton. Observe the rabbit in reactor light and check with the control room to see if the operators I heard the rabbit leave the reflector region. Hearing the rabbit depart the reflector is the only sure way to know it has left. If the rabbit was heard to depart the reflector region, check the other connecting station to see if the rabbit was returned there.
B. Depres., the dispatch button.
C. Repeat steps A and B several times as directed by the control room.
D. If the attempts fail, turn control box off. Go to the other connecting station, line it up for service and repeat steps A and B.
E. If these p ocedures have failed, follow up action will be handled by reactor operations and health physics personnel.
NOTE: IF THE RABBIT IS STUCK OUTSIDE THE REACTOR IT MAY BE FOUND BY SEARCHING THE GUIDE TUBES WITH A RADIATION MONITOR. IF THE RABBIT IS STUCK IN THE REFLECTOR, THE REACTOR MAY HAVE TO BE SHUTDOWN AND THE P-TUBE REMOVED.
VIII.3.5.4 Wet Rabbit If the outside of the rabbit is wet when it is returned from the reactor, notify the control room immediately.
I Rev. 5/02/89 App'd WD1Y\ S0P/VIII-17 ]
Reset
_ l
I f I l
'VIII.3.6 Emergency Return of Rabbit with Malfunctioning
!- P-Tube Control Box Dispatch and return of the rabbit is controlled by solenoids in cabinet located by the seal trench. All solenoids in use are l labeled by letters in the solenoid cabinet. Procedure to be followed in case of a failure at the local station is as follows:
1 A. Remove cover to solenoid cabinet.
B. Turn solenoid power switch off (this de-energizes all solenoids).
NOTE: THIS CLOSES OFF ALL TUBES WHICH WILL RESULT IN A HIGH CONCENTRATION OF AR41 IF THE REACTOR IS OPERATING.
Room 216 - R and J Dispatch solenoids Room 218 - Q and J Dispatch solenoids Room 227 - B and N Dispatch solenoids Room 228 - A and N Dispatch solenoids Refer to solenoid scheddle.
C. Energize the P-tube blowers.
D. Then, " manually" depress following solenoids in solenoid cabinet.
Room 216 - U and L Return solenoids Room 218 - V and L Return solenoids Room 227 - G and 0 Return solenoids Room 228 - H and 0 Return solenoids As an example, the solenoids for return to room 216 should be in the following positions: solenoids R and J "up";
j solenoids U and L "down".
I I
Rev. 5/02/89 App'd SW\ 50P/VIII-18 ]
Reset l
l E__ _ l
VIII.4 Beamport Experiments VIII.4.1 General Requirements As with all other experiments, beamport irradiations and I- measurements must be authorized by an approved TUR.
A. There are four major hazards involved with beamport experi-ments. The are:
- 1. Changes in reactor reactivity due to beanport activities such as draining or flooding a beamport.
- 2. Exposure of personnel to radiation as a result of move-ments of shielding or inadequate shielding.
- 3. Release of radioactive gases such as Ar-41 which are produced in the beamport.
- 4. A production of explosive or toxic materials in the I B.
beamport.
The limitations listed below are established to minimize or eliminate these hazards.
- 1. The AEC Regulations Title 10 Part 50 Section 50.54(j) require that " Apparatus and mechanisms other than con-trols, the operation of which may affect the reactivity or power level of a reactor shall be manipulated only with the knowledge and consent of an Operator or Senior Operator licensed pursuant to Part 55 of this chapter present at the controls." Because of this regulation, all beamport evolutions such as draining, filling or evacuating the port will be done by Reactor Operations personnel. Care must also be exercised in filling a drained beanport. The air within a drained port will be activated during reactor operation and this activated air is forced out of the port during the filling opera-tion. These activated gases present a radiation hazard to personnel in cor',ainment and can also result in a release of radioactive gases in excess of the license limit. This potential hazard is another reason for requiring that only reactor operations personnel be Rev. 5L02/89 App'd V8TG\ SOP /VIII-19 ]
Reset
l permitted to fill, drain, or evacuate a beamport. When-ever practical, all changes in beamport st$tus shall be made only after the reactor has been shutdown for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 2. All shielding movements (including temporary movements which will be returned to normal) shall be coordinated with Health Physics personnel. This restriction is necessary to insure that no personnel radiation hazard is introduced by movement of beamoort shielding.
- 3. The gamma and neutron radiation levels in a beamport can easily induce chemical reactions which would g normally require ext. eme temperature and/or pressure B conditions in the laboratory. The Technical Specifica-tions are quite restrictive on the use of or the generation of explosive materials in an experiment.
An experimenter should evaluate the possibility of the generation of explosives from any materials that are placed in a beamport experiment.
Section VIII.1.2 outlines the limitation on the use of toxic and flammable materials. This section is written to restrict the introduction of toxic and flammable materials in an experiment or in the contain-ment building. The experimenter is cautioned, however, that a toxic or flammable may be generated in a beamport from some perfectly harmless material, and thus should analyze the possible reactions from any material he introduces into his experiment.
l NOTE: The experimental can may be flooded or drained only when the reactor is shutdown.
l l
l l
Rev. 5/02/89 App'd Wm 50P/VIII-20 ] E Reset l
l
<I.
6 VIII.4.2 Beamport "B" Procedures ]
]
CAUTION: THE REACTOR SHALL BE SHUTDOWN BEFORE ANY ]
DRAIN OR FILL OPERATION IS PERFORMED. ]
]
NOTE: All valve changes shall be made by Reactor Operations ]
personnel . The valve manifold for Beamport "B" is ]
under the deck plate below Beamport "A". ]
I A. Filling the Port Liner (or adding water to the port liner) ]
- 1. Check the beam port D1 supply valve open (above the ]
sample station at room 114 entrance), ]
- 2. Open BP-B3 (port inlet valve) until water can be heard ]
entering the pipe trench from the port overflow. ]
- 3. Shut BP-B3. ]
l B. Draining the Port Liner The normal condition of the port liner is flooded. Any
]
3 port draining shall be done as per SMP-23. ]
C. Filling the Experimental Can ]
- 1. Check the beam port DI cupply valve open (above sample ]
station at room 114 entrance). ] -
- 2. Check BP-E5 and BP-B7 closed. ]
- 3. Open BP-BB, BP-BIO, and BP-Bil to line up the experi- ]
mental can surge tank for use. ]
- 4. Open BP-B5 to commence filling the experimental can. ]
Monitor the level in the experimental can surge tank. ]
- 5. When the experimental can surge tank is approximately ]
half full, shut BP-B5. ]
- 6. Leave BP-B8, BP-BIO, and EP-Bil open to provide surge ]
tank volume to allow expansion of water in experimental ]
can during operation. 3
- 7. Update the beam port status on Fuel Inventory Sheet. ]
I Rev. 5/02/89 App'd hM SOP /VIII-21 ]
I
I D. Draining the Experimental Can and Backfilling with Helium ]
]
CAUTION: ALL DRAINED WATER IS HIGHLY TRITIATED AND SHOULD, WHENEVER POSSIBLE, BE COLLECTED IN CONTAINERS
]
]
l RATHER THAN BE ALLOWED TO ORAIN TO PIPE TRENCH. ]
]
]
3 1. Connect a helium bottle with regulator to the line at the top of the experimental ce a surge tank vent, BP-BIl. ]
- 2. Set ther regulator pressure at 5 psi. ]
- 3. Connect tubing to experimental can drain BP-B7, and have ]
containers available to collect all drained water. ]
- 4. Open BP-B7 to commen:e draining the experimental can. ]
- 5. The experimental can is drained when water no longer flows ] ;
through BP-B7
- 6. If the experkental can is being prepared for experimental
]
]
l ,
use, continue to purge helium through BP-B7 for at least ] l 15 minutes. ] ;
- 7. Close BP-7, BP 8, and BP-10. ]
- 8. Remove the helium tank. ] q
- 9. Dispose of the tritiated water as directed by Health Physics ] i (the water usually can be returned to the pool, if the ]
containers used to collect it are clean. ]
- 10. Update the beam port status on the Fuel Inventory Sheet. ] ,
I' I
I I
I Rev. 5/02/89 App'd_j,\W SOP /VIII-22 ]
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t VIII.4.3 'Beamport "C" Procedures ]
CAUTION: THE REACTOR SHALL BE SHUTDOWN BEFORE ANY ]
DRAIN OR FILL OPERATION Is PERFORMED. ]
NOTE: All valve changes shall be made' by Reactor Operations ]
personnel. ]
A. Filling the Port Liner (or adding water to the port liner) ]
- 1. Check the beam port DI supply valve open (above sample -] _
station at room 114 entrance). ]
- 2. Check BP-C14 closed. ]
- 3. Open BP-C3 (port inlet valve), while closely monitoring ]
the port surge tank level. ]
- 4. When the port surge tank is approximately half full, ]
shut BP-C3. ]
B. Draining the Port Liner ]
The normal condition of the port liner is flooded. Any ]
port draining shall be done as per SMP-23. ] {
C. Filling the Experimental Can ]
- 1. Check the beam port DI supply valve open (above sample ]
station at room 114 entrance). ]
- 2. Check BP-C6, BP-C7, and BP-C8 closed. ]
- 3. Open BP-C11 to line up the experimental can surge tank ]
for use. ]
- 4. Open BP-C5 to commence filling the experimental can. ]
Monitor the level in the experimental can surge tank. ]
- 5. When the experimental can surge tank is approximately ]
half full, shut BP-C5. ]
- 6. Leave BP-C11 open to provide surge tank volume to allow ] l expansion of water in the experimental can durir.g opera- ] !
tion. ]
- 7. Update the beam port status on the Fuel Inventory Sheet. ] !
l, Rev. 5/02/89 App'd WfM\ S0P/VIII-24 ]
l l
D. Draining the Experimental Can and Backfilling with Helium ]
CAUTION: ALL DRAINED WATER IS HIGHLY TRITIATED AND SHOULD, ]
WHENEVER POSSIBLE, BE COLLECTED IN CONTAINERS ]
RATHER THAN BE ALLOWED TO DRAIN TO PIPE TRENCH. ]
l
- 1. Connect a helium bottle with regulator to the line at ]
the top of the experimental can surge tank vent, BP-C11. ]
-2. Set the regulator pressure at 5 psi. ]
- 3. Connect tubing to experimental can drain, BP-C7, and ]
have containers available to collect all drained water.' ]
- 4. - 0 pen BP-C7 to commence draining the experimental can. ]
- 5. The experimental can is . drained when water no longer ]
flows through BP-C7. ]
- 6. If the experimental cuo is being prepared for experi- ]
mental use, continue to purge helium through BP-C7 ]
for at least 15 minutes. ]
- 7. Close BP-C7 and BP-Cll. Check BP-08 and BP-C6 closed. ]
- 8. Remove the helium tank. ]
- 9. Dispose of the tritiated water as directed by Health ]
Physics (the water usually can be returned to the pool, ]
if the containers used to collect it are clean). ]
- 10. Update the beam port status on the Fuel Inventory Sheet. ]
l l
l Rev. 5/02/89 App'd bdbW\ , SOP /VIII-25 ]
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l VIII.4.4 Beanport "D" Procedures ]
CAUTION: THE REACIOR SHALL BE SHUTDOWN BEFORE ANY FILL ]
OR DRAIN OPERATION IS PERFORMED. ]
NOTE: All valve changes shall be made by Reactor Operations ]
personnel. ]
A. Filling the Port Liner (or adding water to the port liner) ]
I 1. Check the beam port DI supply valve open (above sample ]
station at room 114 entrance). ]
- 2. Check the port surge tank isolation valves 3P-D12 and ]
BP-D13 open. ]
- 3. Open BP-D3 (port inlet valve) while closely monitoring ]
the port surge tank level. ]
- 4. When the port surge tank is approximately half full, ]
shut BP-03. ] .
l 5. Leave BP-D12 and BP-D13 open to provide surge tank ]
l volume to allow expansion of water in the port liner ]
during operation. ]
B. Draining the Port Liner ]
The normal condition of the port liner is flooded. Any ] .
port draining shall be done as per SMP-23. ] -
- C, Filling the Experimental Can ]
- 1. Check the beam port DI supply valve open (above sample ]
station at room 114 entrance). ]
- 2. Check BP-D6 and BP-D7 closed. ]
- 3. Open BP-08, BP-D10 and BP-Dil to line up the experi- ] ,
mental can surge tank for use. ]
- 4. Open BP-D5 to commence filling the experimental can. ]
Monitor the level in the experimental can surge tank. ]
- 5. When the experimental can surge tank is approximately ]
half full, shut BP-DS. ]
Rev. 5/02/89 App'd A SOP /VIII-27 ]
L
- 6. Leave BP-08, BP-D10, and BP-D11 open to provide surge ]
tank volume to allow expansion of water in the experi- ]
mental can during operation. ]
- 7. Update the beam port status on the Fuel Inventory Sheet. ]
D. Draining the Experimental Can and Backfilling with Helium ]
CAUTION: ALL DRAINED WATER IS HIGHLY TRITIATED AND SHOULD, ]
WHENEVER POSSIBLE, BE COLLECTED IN CONTAINERS ]
]
I RATHER THAN BE ALLOWED TO DRAIN TO PIPE TRENCH.
- 1. Connect a helium bottle with regulator to the line at ]
the top of the experimental can surge tank vent, BP-Dil. ]
- 2. Set the regulator pressure at 5 psi. ]
- 3. Connect tubing to experimental can drain, BP-D7, and ]
have containers available to collect all drained water.' ]
- 4. Open BP-D7 to commence draining the experimental can. ] ,
- 5. The experimental can is drained when water no longer ]
flows through BP-D7. ]
- 6. If the experimental can is being prerared for experi- ]
mental use, continue to purge helium through BP-D7 ]
for at least 15 minutes. ]
- 7. Close BP-07, BP-D8, BP-D10 and BP-Dil. Check BP-D6 ]
closed. ] .
- 8. Remove the helium tank. ] j
- 9. Dispose of the tritiated water as directed by Health ]
Physics (the water usually can be returned to the pool . ]
if the containers used to collect it are clean). ]
- 10. Update the beam port status on the Fuel Inventory Sheet. ]
I I
Rev. 5/02/89 App'd hb SOP /VIII-28 ]
I
l TITLE VALVE ARRAUGEMEUT BEAM D R * * 'N G N O- 1 PORT "D~ l087 RESEARCH REACTOR FACILITY .ggg7 3 op 5 vW UNIVERSITY of MISSOURI. COLUMBIA y II DATE 21 JUNE 1988 DRAWN BY J M. McRe t APP OVED BY U \
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g l Rev. 5/02/89_ App'd [W SOP /VIII-29 ]
I VIII.4.5 Beamport "E" Procedures ]
CAUTION: THE REACTOR SHALL BE SHUTDOWN BEFORE ANY FILL ]
OR DRAIN OPERATION IS PERFORMED. ]
NOTE: All valve changes shall be made by Reactor Operations ]
personnel. ]
A. Filling the Port Liner (or adding water to the port liner) ]
- 1. Check the beam port DI supply valve open (above sample ]
station at room 114 entrance). ]
- 2. Check the port surge tank isolation valves BP-E12 and ]
BP-E13 open. ]
- 3. Open BP-E3 (port inlet valve) while closely monitoring ]
the port surge tank level. ]
- 4. When the port surge tank is approximately half full, ]
shut BP-E3. ]
- 5. Leave BP-E12 and BP-E13 open to provide surge tank ]
volume to allow expansion of water in the port liner 3 during operation. ]
B. Draining the Port Liner ]
The normal condition of the port liner is flooded. Any ]
port draining shall be done as per SMP-23. ]
C. Filling the Experimental Can ] '
- 1. Check the beam port DI supply valve open (above sample ] 1 station at room 114 entrance). ]
- 2. Check BP-E6 and BP-E7 closed. ] .
- 3. Open BP-E8, BP-E10 and BP-Ell to line up the experi- ]
mental can surge tank for use. ] !
- 4. Open BP-E5 to commence filling the experimental can. ]
Monitor the level in the experimental can surge tank. ]
- 5. When the experimental can surge tank is approximately ]
half full, shut BP-E5. ]
I Rev. 5/02/89 App'd M SOP / Vill-30 ]
I
____ 1
I 6. Leave BP-EB, BP-E10, and BP-Ell open to provide surge ]
tank volume to allow expansion of water in the experi- ]
mental can during operation. ]
- 7. Update the beam port status on the Fuel Inventory Sheet. ]
I D. Draining the Experimental Can and Backfilling with Helium ]
CAUTION: ALL DRAINED WATER IS HIGHLY TRITIATED AND SHOULD, ]
WHENEVER POSSIBLE, BE COLLECTED IN CONTAINERS ]
RATHER THAN BE ALLOWED TO DRAIN TO PIPE TRENCH. ]
- 1. Connect a helium bottle with regulator to the line at ]
the top of the experimental can surge tank vent, BP-Ell. ]
- 2. Set the regulator pressure at 5 psi. ]
- 3. Connect tubing to experimental can drain, BP-E7, and ]
have containers available to collect all drained water.' ]
I 4. Open BP-E7 to commence draining the experimental can.
The experimental can 17 drai.ted when water no longer
]
]
5.
flows through BP-E7. ]
- 6. If the experimental can is being prepared for experi- ] !
mental use, continue to purge helium through BP-E7 ] I for at least 15 minutes. ]
- 7. Close BP-E7, BP-E8, BP-E10 and BP-Ell. Check BP-E6 ]
closed. ]
- 8. Remove the helium tank. ]
I
- 9. Dispose of the tritiated water as directed by Health ] ,
Physics (the water usually can be returned to the pool, ]
I if the containers used to collect it are clean). ]
- 10. Update the beam port status on the Fuel Inventory Sheet. ] I I :
I I :
I Rev. 5/02/89 App'd th h SOP /VIII-31 ]
_ _ TITLE
_ _._\% . . n.'L _ . . . _ . . . . . .ARR4!!GEMEHT SEDD5R A *'"0 N o-l PORT *E
- RESEARCH REACTOR FACILITY l007 V' I SHEET 4 OF 9 UNIVERSITY of MIS 8OURI. COLUMBIA
( II DATE 21 JUNE 1988 DRAWN SY
.I M Mcgcc APRROVED BY ww\
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$R) 885 Rev. 5/02/89 App'd hf0VA SOP /VIII-32 ]
\
I I VIII.4.6 Operating Procedures for Beamport "F" ]
The following procedures shall be used for operation of Beamport ]
"F". All valve and tube changes shall be made by Reactor Opera- ]
tions personnel. Major shielding movements and all center tube ]
adjustments or changes shall be coordinated with Health Physics ]
and Reactor Operations personnel. A copy of this procedure ]
shall be posted near Beamport "F" and a copy shall be put in the ]
Beamport "F" log book. ]
CAUTIONS:
- Insure center tabe is not left fully inserted; allow ]
at least 1/4 inch for thermal expansion. ]
- After the center tube is inserted, verify the drain ]
and vent valves are shut. ]
o To prevent a partially filled beam tube leaving a crack ]
for radiation, be sure the vent tank has water in it. ]
- To limit handling of a very radioactive filter tube, ]
pull the tube back four feet and let it decay for > 2 ]
days before withdrawing it. Have Health Physics ]
coverage. ]
- To limit tritium release, limit leakage of water. ]
e To prevent excessive personnel exposure, make sure ]
filter parts are in tube and pushed forward to reactor ]
end of filter tube. Apply vacuum slowly so that filter ]
parts are not sucked back. Have Health Physics coverage ]
on startup. ]
e After startup, check Health Physics readings against ]
previous readings with similar filters. ]
- Make it a Mbit to stay out of beams, whether they are ]
open or " closed". ] ]
]
NOTE: The experimental can may be flooded or drained only ] l when the reactor is shut down. ]
]
Rev. 5/02/89 App'd M SOP /VIII-33 ]
I The water level in the surge tank shall be checked and nain- ]
tained by operations. Makeup water should be " super" water. ]
The principle experimenter should send a note to operations ]
asking for a change in filters and tubes. The note should reach ]
operations before the shutdown. The principle experimenter is ] /
responsible for verifying the desired filtering material is in ]
a center tube before it is inserted and that it is covered in ]
his RUR. To facilitate in verifying materials, all filter parts ]
should be marked and their storage should be controlled because ]
of their activation and potential contamination. ]
A. Installing Center Tubes in Beamport "F" ] *
- 1. Center tubes shall be installed into Beamport "F" only ]
with the reactor shutd an. ]
- 2. Verify the Beacport "F center tube sealing "0"-ring ]
is in place and in good condition. ]
- 3. With Health Physics coverage, transfer the desired ]
center tube from storage to Beanport "F" and insert it ]
until contact is made with the ball valve. Note the ]
change in the Beamport Storage Log. ]
- 4. Lightly tighten the center tube "0"-ring packing nut; ] g check the drain valve and vent valve closed and open ] a the surge tank line valve. ]
- 5. Open the center tube ball valve and insert the center ]
tube. The center tube packing nut may need to be ]
adjusted so the tube can be inserted with minimal ] ,
water leakage. ]
- 6. With the center tube fully inserted, pull the tube out ] l the distance desired by the experimenter. It must be ]
pulled out at least 1/4 of an inch to allow for thermal ]
expansion. ]
- 7. The center tube end plate shall be removed and a rod ] g inserted in the tube to verify the filter slugs are at ] E the end of the tube closest to the reactor core. ]
I Rev. 5/02/89 App'd {MPf(\ SOP /VIII-34 ]
l
- 8. The vacuum pump shall be hooked up and started before ] !
the reactor is taken critical. The vacuum should be ]
applied slowly so that suction will not pull back the ]
filter parts. ]
- 9. A beamport radiation survey shall be completed after ] l the reactor is started up at 10 MW. ]
B. Adjustments to Beamport "F" Center Tube ]
The center tube shall only be adjusted with the reactor ]
suberiti cal . Adjustments include changing the distance the ]
center tube is from the core and pulling or adding parts ] l from the center tube. ]
- 1. Take the reactor suberitical before adjusting the ]
center tube. ]
- 2. If the center tube is moved, insure it is not closer ]
than 1/4 inch from being fully inserted. ]
- 3. After adjustments are made and vacuum restored, return ]
reactor to normal operations, and perform a Beamport "F" ]
radiation survey. ]
C. Removing Center Tube from Beamport "F" ]
The center tubes may be very activated. Therefore, close ]
Health Physics assistance is required. Minimize the ]
number of personnel in Beamports "D", "E", and "F" areas ]
while transferring the center tube. ]
- 1. The center tube should be allowed to decay before ]
I moving from the beamport; preferably at least three ]
days because of tho sodium activity. ]
- 2. After loosening the packing nut, pull the center tube ]
back slowly drying the center tube as it is being with- ]
drawn. ]
- 3. When the center tube is one to two feet from being fully ]
withdrawn, attempt to gently close the ball valve (be ]
careful not to score the valve or the center tube). ]
I I Rev. 5/02/89 App'd N A SOP /VIII-35 ]
- 4. When the ball valve closes, stop withdrawing the center ]
tube; close the surge tank line valve, then open the ]
vent and drain' valves. ]
l 5. Completely remove the center tube. ]
- 6. Transfer the center tube to a beamport storage hole, ]
log the change in the storage oook, and survey around ]
the storage hole. ]
I I
I Rev. 5/02/89 App'd(MM SOP /VIII-36 ]
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VIII.5 Handling and Release of Irradiated Samples VIII.5.1 General Responsibilities The Reactor Services Engineer shall coordinate the handling and shipping of all samples irradiated in the in-pcol facilities.
He shall ensure that the shipping container is in conformance ]
with the applicable regulation and that all required shipping papers and documents are prepared in a timely manner.
The Services Engineer shall also coordinate the sample j handling with Health Physics personnel.
The Shift Supervisor shall have the responsibility of i ensuring that all irradiation records are complete. He will ] '
immediately notify the Services Engineer of any apparent l discrepancies relating to the in-pool irradiations.
VIII.5.2 Sample Handling Procedures Detailed procedures for the handling of various samples are contained in the Health Physics Standard Operating procedures.
VIII.6 Response Procedures for the Nuclepore Irradiation Facility The following procedures shall be used when responding to alarms for the Nuclepore Irradiation Facility.
VIII.6.1 Automatic system shutdown trip alarms require the following i
(
action:
A. Verify the film drive motor has stopped.
B. Verify the rabbit has retracted to the full out position.
C. Time and date the film roll.
D. Notify the Nuclepore system technician. )
i l
l Rev. 5/02/89 App'd DN\ SOP /VIII-38 ]
l
_ _ _________ J
i Those alarms are as follows:
- 1. System failure alarm
- 2. Large roll alarm
- 3. Take-up dancer alarm
- 4. Supply dancer alarm
- 5. Gas system alarm
- 6. Drive power alarm VIII.6.2 Alarms having no automatic function require that you either remedy the cause of the alarm or shut the system down. The alarms are as follows:
A. High oxygen concentration alarm
- 1. Increase the helium flow.
I 2. If you are unable to immediately reduce 02 concentra-tion, shut down the system and withdraw the rabbit.
Contact the Nuclepore system technician.
B. Helium supply alarm 1.- Place a new helium bank on supply.
- 2. If the alarm does not clear, shut down the system and contact the Nuclepore system technician.
C. Alarm function failure alarm
- 1. Shut down the Nuclepore system and notify the Nuclepore system technician.
D. PISH-5 alarm I 1. If the PISH-5 low alarm light is on at Cabinet B, shut down the system and notify the Nuclepore system technician.
E. Small roll alarm
- 1. Note the time and prepare to shut down the system at the prearranged interval specified by the Nuclepore system technician.
Rev. 5/02/89 App'd h SOP /VIII-39 ]
F. Reactor off-gas stack high activity
- 1. If the Nuclepore Irradiation Facility is suspected to be the cause of the stack high activity alarm, secure the system. Verify rabbit is fully retracted.
- 2. Notify Health Physics and Shift Supervisor.
- 3. Contact the Nuclepore system technician.
NOTE: A comprehensive systems procedure and systems description manual provided by the Nuclepore Company is located at the.
system operating station for emergency reference.
VIII.7 Thermal Column Door Operations VIII.7.1 Opening The Thermal Column Door NOTE: Do not open thermal column door with the reactor critical.
- 1. Clear all obstructions from behinu thermal column door.
- 2. Verify air off to Radiograph with Control Room.
- 3. Disconnect air supply line on thermal column door at the snap fitting.
- 4. Verify Neutron Radiograph rotating aperture drive shaft pulled back and disconnected.
- 5. Preparation of Nuclepore Case:
A. Decouple Nuclepore take-up shaft.
B. Remove alignment pins from shield box door.
C. Roll shield box cover as far back along track as possible. (NOTE: If thermal column door must be backed out further than this, attach shield box door lifting rig and move to south side of the platform using the building crane.)
Rev. 5/02/89 App'd hPW\ SOP /VIII-40 ]
Reset
..-_____________________-_-__Y
D. Decouple Nuclepore drive shaft.
Decouple Nuclepore rabbit drive. (NOTE:
E. Remove rubber grommet and store.)
F. Secure air to the Nuclepore equipment.
G. Disconnect PVC air lines to the drive roll.
- 6. Unstack shielding as necessary to allow free movement of the door.
- 7. ' Plug in thermal column door drive motors (2).
- 8. Back out thermal column door approximately six (6) inches.
- 9. Disconnect four (4) PVC lines connected to the top of the Nuclepore Irradiator Case.
- 10. With Health Physics coverage, open the thermal column door to the desired position.
VIII.7.2 Shutting The Thermal Column Door
- 1. Shut the thermal column door far enough to allow the four (4) PVC lines to be reconnected to the Nuclepore Irradiator Csse.
- 2. Reconnect the four (4) PVC lines.
- 3. Completely shut the thermal column door while monitoring to ensure that the four (4) PVC lines do not become pinched off. ]
- 4. Verify the thermal column door open limit switch has cleared in the Control Room.
l 5. Verify Neutron Radiograph rotating aperture drive shaft will mate properly.
I NOTE: Do g rotate aperture.
- 6. Unplug the thermal column door drive motors.
- 7. Restack shielding on the top of the thermal column.
- 8. Connect the Radiograph air supply line to the regulator assembly. l
- 9. Install the platform deck plates.
I Rev. 5/02/89 App'd { 50P/VIII-41 ] ,
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- 10. Nuclepore Experiment:
[.
'l A. Recouple and lock Nuclepore drive roll. g B. Attach PVC air lines to the drive roll. E C. Install rubber grommet and attach rabbit drive mechanism.
D. Place shield box door back on rails and shut it. Pin door fully shut.
E. Recouple take-up spline coupling.
F. Open Nuclepore air supply valve and reset all tension cont rol s .
G. Test run film.
H. Place the experiment in its desired operational mode in accordance with approved procedures.
- 11. Inform. operators of the system status.
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I Rev. 5/02/89 App'd - (J M SOP /VIII-42 ]
Reset
I l REACT 0R EMERGENCY PR0CEDURES I
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p REACTOR EMERGENCY PROCEDURES i-TABLE OF CONTENTS Section No. Page No..
REP-0 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . REP-0-2 ]
REP-1 FAILURE TO SCRAM OR R0D RUN-IN . . . . . . . . . . . . . . . REP-1-1 REP-2 REACTOR SCRAM FROM CAUSES OTHER THAN LOSS OF FLOW OR PRESSURE . . . . . . . . . . . . . . . . . . . . . . . . REP-2-1 REP-3 REACTOR SCRAM FROM LOSS OF PRIMARY SYSTEM PRESSURE OR FLOW . . . . . . . . . . . . . . . . . . . . . . . . . . REP-3-1 l
l REP-4 HIGH RADIATION . . . . . . . . . . . . . . . . . . . . . . . . REP-4-1 REP-5 NUCLEAR INSTRUMENT FAILURE . . . . . . . . . . . . . . . . . . REP-5-1 REP-6 FAILURE OF THE AREA RADIATION MONITORING SYSTEM (ARMS) . . . . REP-6-1 REP-7 LOSS OF COMMUNICATIONS BETWEEN REACTOR CONTROL ROOM AND EXPERIMENTERS . . . . . . . . . . . . . . . . . . . . . REP-7-1 REP-8 CONTROL R00 ORIVE FAILURE . . . . . . . . . . . . . . . . . . REP-8-1 REP-9 ELECTRICAL ANOMALIES . . . . . . . . . . . . . . . . . . . . . REP-9-1 REP-10 FAILURE OF EXPERIMENTAL APPARATUS . . . . . . . . . . . . . . REP-10-1 REP-11 LOW FIRE MAIN PRESSURE . . . . . . . . . . . . . . . . . . . . REP-11-1 REP-12 LOSS OF SERVICE WATER TO FACILITY . . . . . . . . . . . . . . REP-12-1 REP-13 LOSS OF SECONDARY FLOW . . . . . . . . . . . . . . . . . . . . REP-13-1 REP-14 LOSS OF POOL FLOW DURING REACTOR OPERATION . . . . . . . . . . REP-14-1 FEP-15 LOSS OF P0OL WATER LEVEL DURING REACTOR OPERATION . . . .. . . REP-15-1 REP-16 VALVES 507A AND 507B FAIL TO CLOSE . . . . . . . . . . . . . . REP-16-1 REP-17 PRESSURIZER VALVES FAIL TO OPERATE . . . . . . . . . . . . . . REP-17-1 REP-18 BOTH ANTISIPHON VALVES (543A AND 543B) FAIL TO OPEN . . . . . REP-18-1 REP-19 FAILURE OF EMERGENCY CORE COOLING VALVES (546 A/B) . . . . . . REP-19-1 REP-20 HIGH ACTIVITY LEVELS IN THE PRIMARY COOLING SYSTEM (FPM) . . . REP-20-1 REP-21 HIGH STACK MONITOR INDICATIONS . . . . . . . . . . . . . . . . REP-21-1 REP-22 BOMB OR OTHER OVERT THREATS . . . . . . . . . . . . . . . . . REP-22-1 Rev. 5/02/89 App'd (Mpyy\ REP-0-1
REACTOR EMERGENCY , '9CEDURES INTRODUCTION
'It cannot be overly stressed that the guideline for any emergency procedure shall be actions which safeguard personnel and equipment, in that order.
If, while operating the University of Missouri Research Reactor, a situation develops that requires an emergency action as set forth in these procedures, it must be remembered that for a transient type accident, Title 10 of the Code of Federal Regulations, Part 50.36, dictates certain actions as pertaining to safety limits and limiting safety system settings. In the case of a transient type accident, the Shift Supervisor must determine before resuming operation if a safety limit, as illustrated by the safety limit curves set forth in the MURR Technical Specifications has been exceeded. If, in fact, a limit has been exceeded, the reactor shall remain shutdown until the Commission authorizes resumption of opera-tion. 1.imiting safety settings are those settings which will initiate autonatic action to prevent exceeding a safety limit. If a safety system setting is exceeded without receiving an automatic function trip, the reactor shall be shut down and the Commission notified. The cause of the failure will be noted and corrective action taken before operations resume.
The following actions shall be taken by reactor operating personnel for the conditions listed.
1 Rev.7[30/85 App'd REP-0-2 ]
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REP-1 FAILURE TO SCRAM OR ROD RUN-IN i
IF, for any reason, the reactor fails to scram or rod run-in automatically when caTled for by the protective system, the reactor operator shall:
.I IMMEDIATE ACTIONS:
- 1. Scram the reactor.
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- 2. Ensure all the rods are full in.
- 3. Ensure the reactor is shutting down as indicated by nuclear ;
instrumentation. i SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor of scram.
- 2. Verify that safety limits and LSSS were not exceeded.
- 3. Make console log entry and fill out UNSCHEDULED SHUTDOWN report.
- 4. Determine and correct the problem before resuming operation.
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Orig. 7/03/85 App'd dbYY\ REP-1-1
REP-2 REACTOR' SCRAM FROM CAUSES OTHER THAN LOSS OF FLOW OR PRESSURE IMMEDIATE ACTIONS:
- 1. Acknowledge.cause of. scram and.take corrective actions as required.
- 2. Monitor nuclear instrumentation to assure reactor is shutting down.
1
- 3. . Verify the blades are full in and rod drive mechanisms driving in.
SUBSEQUENT ACTIONS:
1.- Notify the Shift Supervisor of scram.
- 2. . Make console' log entry and fill out UNSCHEDULED SHUTDOWN report.
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Orig. 7/03/85 App'd M REP-2-1 m1) -repr-i rr as .
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i REP-3 REACTOR SCRAM FROM LOSS OF PRIMARY !
SYSTEM PRESSURE OR FLOW ,
IMMEDIATE ACTIONS: ;
I.
- 1. Acknowledge the cause of scram. ;
- 2. Check that' primary system is in normal shutdown lineup.
- 3. Check for AT across the in-pool heat exchanger. !
- 4. Monitor nuclear instrumentation to assure reactor is shutting down. ,
i SUBSEQUENT ACTIONS: i
- 1. Notify the Shift Supervisor of scram.
- 2. Place primary system switches and controls in normal shutdown mode.
- 3. Make console entry and fill out UNSCHEDULED SHUTDOWN report. l I
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I Orig. 7/03/85 App'd (dh REP-3-1
REP-4 HIGH RADIATION A. IF increase in radiation levels above normal is detected before any trip Tiivel occurs; the operator shall:
IMMEDIATE ACTIONS:
- 1. Notify the Shift Supervisor.
SUBSEQUENT ACTIONS:
- 1. Closely monitor the radiation level.
- 2. The Shift Supervisor may lower reactor power to prevent continued rise in radiation levels.
- 3. hotify the Manager of Reactor Health Physics.
B. IF, the alarm trip point jji, exceeded, the operator may:
IMMEDIATE ACTIONS:
- 1. At the discretion of the Shift Supervisor, initiate a roo run-in.
SUBSEQUENT ACTIONS:
- 1. Notify the Reactor Manager.
- 2. Notify the Manager of Reactor Health Physics.
1 C. In the event radiation levels have reached a magnitude to cause reactor isolation, procedures outlined in FEP-2 shall be followed.
Orig.7/03/85 App'dMDM REP-4-1
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REP 5 NUCLEAR INSTP.UMENT FAILURE IF any nuclear instrument channel required for reactor operation
- is d;tefmTned to not function correctly and the reactor has not scrammed due to instrenent' failure, the reactor operator shall:
IMMF01 ATE' ACTIONS:
- 1. Scram the reactor.
SUBSEQUENT ACTIONS:'
1._ Notify the Shift; Supervisor.
- 2. The nuclear instrument channel shall be repaired and tested prior to
' restart 1_ng the reactor.
- 3. Make console log entry and fill out UNSCHEDULED SHUTDOWN report.
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l CNOTE: ALL SIX NUCLEAR CHANNELS REQUIRED TO BE OPERATIONAL FOR
-REACTOR STARTUP; CHANNELS 2 THROUGH 6 REQUIRED OPERATIONAL DURING OPERATION AT POWER.
' Orig. 7/03/85 App'd h REP-5-1 1
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l I REP-6 FAILURE OF THE AREA RADIATION MONITORING SYSTEM (ARMS)
A. FAILURE OF BUILDING AIR PLENUM OR REACTOR BRIDGE (ARMS)
IMMEDIATE ACTIONS:
- 1. Scram the reactor. ]
- 2. Notify th; Shift Supervisor. ]
SUBSEQUENT ACTIONS:
- 1. Notify the Manager of Reactor Health Physics.
- 2. Switch inputs from the detector in offgas duct, or reactor ]
bridge to operational monitors to determine if the detector ]
is functioning. ]
- 3. IF the detector for the affected area is functioning, it may Temain connected to the operational monitor to which it was switched, while the affected area monitor is being repaired.
- 4. Portable monitoring equipment shall be set up to monitor radiation in the displaced area.
- 5. The reactor may return to operation. ]
B. FAILURE OF ARMS OTHER THAN SPECIFIED IN "A":
- 1. Temporary or portable monitoring equipment may be set up to monitor radiation levels.
- 2. Notify the Shif t Supervisor.
- 3. Notify the Manager of Reactor Health Physics.
Rev. 5/02/89 App'd hh REP-6-1
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REP-7
- ' LOSS'0F COMMUNICATIONS BETWEEN REACTOR CONTROL-ROOM AHD EXPERIMENTERS
-? A. ~ DURING REACTOR STARTUP'
- 1. The ' reactor, shall be held steady at the existing power until repairs or' temporary communication can be established.
S B. DU' RING STEADY STATE
- 1. If. repairs or' temporary' communications cannot be made in a reasonable period:of time, the reactor shall be shut down.
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l Orig. 7/03/85 App'd M REP-7-1
l Il !
i REP-8
- CONTROL ROD ORIVE FAILURE IF the reactor operator detects a steck or inoperative drive mechanism, he sha W:-
i E IMMEDIATE ACTIONS:
- 1. Scram the reactor, noting approximate stuck position.
- 2. Place master switch in test to prevent mechanisms from driving in.
- 3. Verify the reactor is shutting down by nuclear instrumentation.
SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Disconnect power to affected rod drive mechanism and install dummy load test connector.
l 3. Insert unaffected mechanisms manually.
Make console log entry and fill out UNSCHEDULED SHUTDOWN report.
4.
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I Orig. 7/03/85 App'd h REP-8-1
REP-9 E_LECTRICAL ANOMALIES NOTE: AN ANOMALY SUCH AS SINGLE PHASING OR A REDUCTION IN LINE VOLTAGE MAY NOT BE OBVIOUS. THE REACTOR MAY OR MAY NOT SHUT DOWN. SYMPT 0MS MAY INCLUDE DIMMING OF LIGHTS, LOSS I OF SOME CONTAINMENT LIGHTS OR LOSS OF SOME PROCESS SYSTEM EQUIPMENT.
l A. SINGLE PHASING OR LOW LINE VOLTAGE In the event of a single phasing or low voltage condition, the reactor I operator shall:
IMMEDIATE ACTIONS:
- 1. Scrrm the reactor /or if already scrammed, check reactor shutdown.
Turn 0FF all pump and cooling tower fans in an expeditious I 2.
manner.
- 3. Place all valve controls in their normal shutdown position and I manual mode.
- 4. Trip the auto transfer switch on substation "B".
SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Check emergency generator and its loads for proper operation.
- 3. Determine cause of electrical anomaly and try to remedy it.
I 4. If a rabbit is in the reactor, transfer P-tube blower to emergency power and return the rabbit.
- 5. Trip the supply breakers for MCC-1, MCC-2A AND MCC-2B in cooling tower.
I Orig. 7/03/85 App'd M REP-9-1 I
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' I RECOVERY ACTIONS: f
- 1. Check all three phases on each substation for proper voltages.
.I
- 2. When starting systems, closely monitor any equipment known to be ] l running at.the time the electrical anomaly was noted. 1 l
- 3. A Full Power Startup Checksheet shall be performed prior to ] i starting up the reactor. !
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Rev. 5/02/89 App'd id h REP-9-2 g
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B. SUSTAINED LOSS OF ELECTRICAL POWER IMMEDIATE ACTIONS:
- 1. Check the reactor shutdown.
- 2. Turn 0FF all pump and cooling tower fan switches.
- 3. Place all valve controls in their normal shutdown position and manual mode.
- 5. Trip the master supply breaker on substation "B".
SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Check emergency generator and its loads for proper operation.
- 3. Check gas tank level and project remaining run time of E. G.
- 4. Determine cause of electrical power loss.
- 5. If a rabbit is in the reactor, transfer P-tube blower to emergency I power and return the rabbit.
- 6. Trip the supply breakers for MCC-1, MCC-2A and NCC-2B in cooling tower.
- 7. Make console log entry and fill out UNSCHEDULED SHDTDOWN report.
RECOVERY ACTIONS:
- 1. Check all three phases on each substation for proper voltages.
- 2. When starting the system, closely monitor any equipment known to be running at the time of the electrical power loss.
- 3. A Full Power Startup Checksheet shall be performed prior to starting up the reactor.
1 C. MOMENTARY LOSS OF ELECTRICAL POWER:
(only a reactor scram occurred)
- 1. Notify the Shift Supervisor.
- 2. Verify momentary loss of electrical power with power plant.
- 3. The reactor may be operated after performing a Reactor Short Form Precritical Checksheet.
- 4. Make console log entry and fill out UNSCHEDULED SHUTDOWN report.
Orig. 7/03/85 App'd (Npff\ REP-9-3 l !
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I; I REP-10 FAILURE OF EXPERIMENTAL APPARATUS
~
.Upon receiving reliable information that experimental equipment is oper-ating in a manner hazardous to personnel and the hazard is due to radiation from the reactor, the reactor operator shall:
I IMMEDIATE ACTIONS:
- 1. Reduce power by rod run-in.
- 2. Secure the experiment or keep personnel away.
- 3. If the problem is significant enough to require control room personnel, shut down the reactor and return experiment to a safe condition.
SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
l 2. Repair experiment or place in safe condition before restarting the reactor.
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Orig. 7/03/85 App'd hCyN\ REP-10-1 I
I I REP-11 LOW FIRE MAIN PRESSURE IMMEDIATE ACTIONS:
- 1. Send operator to fire main pressure gauge to determine pressure.
- 2. If pressure remains below minimum pressure required by last Emergency Pool Fill Flow Test (CP-16), shut down the reactor.
I SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Determine cause for fire main low pressure.
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I Orig. 7/03/85 App'd hN REP-11-1 I
REP-12 I LOSS OF SERVICE WATER TO FACILITY Upon loss of the water service to the facility, the reactor operator shall:
IMMEDIATE ACTIONS:
- 1. Shut down and secure the reactor.
SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Announce to entire facility that water service has been interrupted.
- 3. Secure and tag out the following equipment: ]
- a. Secondary Pumps P1, P2, P3, and P4 (P4 can be left on for ]
building A/C support at the discretion of the Shift Supervisor. ]
- b. Emergency Generator Unit
- c. Main Air Compressor
- d. Vacuum Unit Pumps
- e. Air Conditioning Units
- f. Hot Water Recirculating Pump
- g. - After the reactor has been secured, secure the primary coolant water system since pumps P501 A/B no longer have cooling water.
- h. Room 212 (North Counting Room) Air Conditioner (Notify Research and Applications Group)
- 1. Room 232B (ETSRC Counting Room) Air Conditioner (Notify Research and Applications Group.)
I j. Room 260 air conditioning unit ]
- k. Ice Machine (inner passage way) ]
- 1. Control room water heater ]
- m. Record in Reactor Log that the machinery above has been tagged ]
out as per REP-12. ]
- 4. Upon restoration of water to the Facility, return all systems to r:ormal status.
- 5. Announce to entire Facility the restoration of water service.
Rev. 5/02/89 App'd M REP-12-1 1
REP-13 LOSS OF SECONDARY FLOW A. GRADUAL FLOW REDUCTION. ,
_IF, F secondary flow is gradually decreasing, the Reactor Operator shall:
IMMEDIATE ACTIONS _:
- 1. Send the Assistant Duty Operator to the cooling tower to l
assess the flow reduction problem. (see NOTE below) l
- 2. Switch secondary pumps to determine whether the action corrects the deteriorating flow conditions.
- 3. Notify the shift supervisor. ,
- 4. Monitor the position of S-1 and reactor temperature.
- 5. IF primary / pool temperature cannot be managed, the reactor shall FE shut down, leaving primary and pool systems in operation.
NOTE: A LOSS OR REDUCTION IN SECONDARY FLOW MIGHT BE CAUSED BY:
a) Mechanical failure of a secondary cooling pump.
b) Air binding of a secondary cooling pump.
c) A break in the secondary cooling line.
d) Loss of water in the cooling tower causing pump to shut off when low sump level switch is tripped.
l_
e) Restriction in flow due to a faulty check valve on the discharge side of a running pump. ]
f) Failure in low sump level cutout circuitry (proper sump level, but pumps trip off).
- g. Clogged suction strainer.
l SL'3 SEQUENT ACTIONS:
- 1. Determine cause of flow reduction and determine effects on further operation.
Rev. 5/02/89 App'd (b REP-13-1 I
I B. COMPLETE LOSS OF SECONDARY FLOW IMMEDIATE ACTIONS:
- 1. IF loss of flow is due to loss of secondary pump or pumps, start
- tee standby pump.
- 2. IF the standby pump cannot be put on the line, reduce reactor power Ty' rod run-in to less than 100 KW.
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- 3. Notify the Shift Supervisor.
SUBSEQUENT ACTIONS:
- 1. IF the sump level is normal and pumps cannot be started, bypass tee low sump cutout circuitry and try to restart the pumps.
- 1. IF secondary flow cannot be returned to maintain reactor operating Tivels, the reactor should be shut down.
- 2. Return secondary system to normal before restarting the reactor.
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Orig. 7/03/85 App'd (Ab REP-13-2 I
I REP-14 LOSS OF POOL FLOW DURING REACTOR OPERATION IF pool flow rate drops below 435 gpm in either loop without generating
- an autiiiiiatic scram, the reactor operator shall:
IMMEDIATE ACTIONS:
4
- 1. Scram the reactor.
I %. Shut down the pool sy:: tem, leaving the primary and secondary on the line.
I SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Determine the cause of pool flow loss and correct it before rettarting the reactor.
- 3. Make console log entry and fill out UNSCHEDULED SHUTDOWN reports.
Orig. 7/03/85 App'd hM REP-14-1
REP-15 LOSS OF P0OL WATER LEVEL DURING REACTOR OPERATION IF the pool level becomes less than the RRI limit (= 29 ft.) and continues to reclide:
IMMEDIATE ACTIONS:
- 1. Scram the reactor.
- 2. Notify the Shift Supervisor.
- 3. Secure P508A and B and verify valve 509 closes.
- 4. Secure P513B.
- 5. Place master switch (IS1) in TEST position.
- 6. Manually close valve 509 if it has not closed automatically.
- 7. Close valve 547 by activating the manual 3-way valve on the upper bridge level.
- 8. Ensure valve 547 has closed by local activator indication or light indication in control room.
At this point, the pool is isolated from the process leg of the pool cooling system.
CAUTION: INCREASED RADIATION LEVELS DUE TO LOW POOL LEVEL MAY CAUSE A REACTOR ISOLATION. EVACUATE ALL PERSONNEL EXCEPT FE0 MEMBERS ]
FROM CONTAINMENT. THIS TYPE OF EMERGENCY HAS CONSEQUENCES ]
SEVERE EN0 UGH TO WARRANT VOLUNTARY EMERGENCY LEVEL EXPOSURES ]
UP TO 25 REM BY FE0 PERSONNEL TO MITIGATE THE CONSEQUENCES TO THE GENERAL PUBLIC. MONITOR RADIATION LEVELS CLOSELY FOR RADIATION DOSE ASSESSMENT.
SUBSEQUENT ACTIONS:
IF pool level stops decreasing, continue with section (A). If level continliis to decrease, go to section (B).
Rev. 5/02/89 App'd h REP-15-1 im --------ii----iimem i e
A. LEAK ON PROCESS SIDE OF V509
- 1. Enter room 114 observing proper radiation protection.
- 2. Attempt to locate and secure the leak with all available means.
- 3. Efforts should be made to contain the leakage in the room 114 pipe trench, the labyrinth sump and waste tanks (i.e., secure labyrinth sump' pump when waste tanks are full).
, NOTE: THE PIPE TRENCH AND LABYRINTH SUMP VOLUME (T0 A HEIGHT EQUAL 1
TO THE TOP 0F PIPE TRENCH) IS APPR0XIMATELY 14,000 GALLONS.
- 4. If the pool level had receded to a point that a higher than normal radiation level was creitt;d on the bridge, water from T300 and T301 should be added to res.x the radiation levels.
- 5. Perform recovery action > as per section (D).
B. LEAK INSIDE V509 OR THROUGH BEAMPORTS
- 1. Activate the FE0 as per SEP-1.
- 2. Isolate containment of all but FE0 members.
- 3. Check beamport floor and room 114 tunnel to determine the source of the leak.
- 4. IF the leak is through the beamports go to Section (C). -
IF the leak is Tiiside V509 continue:
- 5. Continue to operate the primary system and secondary system, g possible.
- 6. Secure the tunnel and cooling tower sump pumps.
- 7. Efforts should be made to contain the leakage in the room 114 pipe trench, the labyrinth sump and waste tanks (i.e., secure labyrinth sump pump when waste tanks are full).
NOTE: THE PIPE TRENCH AND LABYRINTH SUMP VOLUME IS APPR0XIMATELY 14,000 GALLONS.
- 8. If leak cannot be secured, and a core void is suspected, open the emergency pool fill valve under the floor plate at the pool edge to open. This will commence filling the facility to the ground level (covering the core).
9< Perform a facility evacuation.
- 10. Perform recovery actions as per section (D).
Orig. 7/03/85 App'd hfhW\ REP-15-2
C. LEAK THROUGH BEAMPORT
- 1. Isolate containment of all but FE0 members. )
- 2. Continue to operate the primary and secondary systems. \
- 3. Secure the tunnel and cooling tower sump pumps.
- 4. Efforts should be made to contain the leakage in the room 114 pipe trench, the labyrinth sump and waste tanks (i.e., secure labyrinth sump pump when waste tanks are full).
NOTE: THE PIPE TRENCH AND LABYRINTH SUMP VOLUME IS APPROXIMATELY 14,000 GALLONS.
- 5. Observing proper radiation protection, begin dismantling the experiment at the suspected beamport so attempts to stop the leak can be performed.
- 6. Perform recovery actions of section (D).
D. REC 0VERY FROM SIGNIFICANT P0OL LEAK
- 1. Repair cause of leak.
- 2. Install necessary piping to interconnect waste system and pool system.
- 3. Return pool water to pool after filtering as much as possible, as per SMP-11, APPEfiDIX II.
Orig. 7/03/85 App'd & REP-15-3
REP-16 VALVES 507A AND 507B FAIL TO CLOSE IF these valves fail to close, the reactor operator shall:
I -
IMMEDIATE ACTIONS:
- 1. Place the master control switch (IS1) to TEST.
- 2. Place the 507A and/or 507B AUT0/ MANUAL switch to MANUAL.
- 3. Place the OPEN/CLOSE switch to CLOSE.
I SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Determine cause of failure of the 507 valves and correct before continuing reactor operation.
NOTE: FAILURE OF THESE VALVES TO CLOSE' PRESENTS A PROBLEM ONLY IN THE EVENT OF A PIPE RUPTURE OR OUT OF POOL LEAK IN THE PRIMARY SYSTEM. CHECK VALVE 502 BACKS UP THE FAILURE OF 507B PREVENTING DRAINING OF THE CORE AND THE ANTISIPHON SYSTEM PREVENTS CORE DRAINING IN CASE OF 507A FAILURE.
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1 Orig. 7/03/85 App'd @ REP-16-1
t REP-17 PRESSURIZER VALVES FAIL TO OPERATE In the event of malfunction of any of the pressurizer valves, such that they cannot be closed from the control room, the reactor operator shall:
l-IMMEDIATE ACTIONS:
1 Shut down the reactor.
- 2. Close the appropriate manual isolation valve in-line with the failed valve.
1 SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Determine cause of malfunction and correct the malfunction of the pressurizer valve before continuing reactor operation.
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Orig. 7/03/85 App'd kM REP-17-1 I
I REP-18 BOTH ANTISIPHON VALVES (543A AND 5438) FAIL TO OPEN IMMEDIATE ACTIONS:
- 1. Open 543A or 543B manually with T-wrench.
- 2. If unsuccessful, close the air supply valve and disconnect copper tubing on .the valve side of 3-way solenoids for 543A or 543B.
- 3. If the valve has not opened, use the T-wrench to manually open the valve.
- 4. If all attempts fail to open either valve and a void core is suspected, carry out the Reactor Isolation Procedure (FEP-2).
- 5. Notify the Shift Supervisor.
NOTE: EITHER VALVE (543A OR 5438) WILL PERFORM THE DESIRED FUNCTION.
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I I I I Orig. 7/03/85_ App'd N(h(v\ REP-18-1
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REP-19 FAl?.URE OF EMERGENCY CORE COOLING VALVES (546 A/B)
I A. BOTH VALVES FAIL TO OPEN FOLLOWING SCRAM FROM LOSS OF PRESSURE OR FLOW IMMEDIATE ACTIONS:
- 1. Place master control switch in TEST.
- 2. Place the valve 546 A/B AUT0/ MANUAL switch in MANUAL.
- 3. Place the valve 546 A/B OPEN/CLOSE switchs in OPEN.
- 4. Notify the Shift Supervisor.
E the valve or valves have still not opened:
- 5. Open the valve manually with T-wrench.
- g 6. If unsuccessful, close the air supply line to the valve at the l l bridge and disconnect copper tubing on the valve side of the i 3-way solenoid.
i I 7. If the valve has not opened, use the T-wrench to manually open the valve. ,
- 8. IF all attempts fail to open one of the valves, operate the l primary and secondary cooling systems.
1 B. ONE OR BOTH VALVES FAIL OPEN DURING REACTOR OPERATION IF indication is received that one or both valves have opened and the reactor has not scrammed *; the reactor operator shall: .
IMMEDIATE ACTIONS-
- 1. Scram the reactor.
- 2. Notify the Shift Supervisor.
- NOTE: IF 546 A/B OPENS DURING OPERATION, A FLOW PATH FOR THE PRIMARY C0OLANT BYPASSING THE CORE IS ESTABLISHED (ABOUT 30 - 33% OF ORIGINAL CORE FLOW). l I
THIS REDUCED FLOW WILL NOT LEAD TO CORE DAMAGE S0 LONG AS NORMAL TEMPERA-TURE, POWER AND PRESSURE ARE MAINTAINED. THIS REDUCED FLOW RATE, HOW-EVER, DECREASES OUR SAFETY MARGIN FROM THE SAFETY LIMIT CURVES BY ABOUT I 60%, S0 THE REACTOR IS TO BE SHUT DOWN UPON RECEIPT OF THIS ACCIDENT (THE CORE AP SCRAM FROM DPS 929 SHOULD HAVE INITIATED AUTOMATICALLY BY ONE OR BOTH 546 VALVES OPENING).
I Orig. 7/03/85 App'd Irfv\ REP-19-1
REP-20 HIGH' ACTIVITY LEVELS IN THE PRIMARY COOLING SYSTEM (FPM)
Upon receiving indication of an abnormally high level of radioactivity in the primary cooling system, the reactor operator shall:
IMMEDIATE ACTIONS:'
- 1. Scram the reactor.
SUBSEQUENT ACTIONS:
ql 1. Notify the Shift Supervisor and Manager of Reactor Health Physics.
- 2. Monitor stack. monitoring system indications closely to determine ]
if an event should be classified as per Site Emergency Procedures ]
(SEP). Use guidelines in REP-21, High Stack Monitor Indications. ]
- 3. Precautionary reduction of flow - secure one pump to decrease flow by 3 one-half.
NOTE: THIS ACTION ASSUMES WORST CASE CONDITION, A FUEL ELEMENT FAILURE. THE REDUCED FLOW IS TO MINIMIZE PLATE EROSION.
- 4. Determine the source of radioactivity and magnitude of activity by: ]
WARNING: EXTREME CAUTION SHOULD BE OBSERVED WHEN ENTERING AREAS CONTAINING PRIMARY COOLANT. THESE AREAS SHOULD BE MONITORED BY bIALTH PHYSICS BEFORE ENTRY. ADEQUATE PROTECTIVE MEASURES SHOULD BE TAKEN BEFORE ENTERING THESE AREAS.
- a. Checking fission product monitor.
- b. Observing off-gas recorder if primary system should automatically vent.
- c. Having primary water sample analyzed.
- d. Conducting radiation surveys in areas containing primary coolant.
Rev. 5/02/89 App'd M REP-20-1 l_
- 5. IF the source of activity is determined to be fission products, a ]
Tiirther reduction of primary flow to approximately 500gpm is necessary to reduce plate erosion. To accomplish this:
- a. Fully open the bypass valve (538A or 5388) around the pump that is running.
- b. Throttle valves 540 A and B.
- 6. Clean up contaminated systems by: )
- a. Leaving the primary cooling and primary cleanup loops in operation to clean up the primary system.
WA!!NING: THE RADIATION LEVELS IN THE DEMINERALIZED ROOMS MAY BE EXTREMELY HIGH.
- 7. When equipment and personnel are ready to identify the leaking fuel ]
element, the primary systems should be shut down as per S0P IV.2.
WARNING: DO NOT ENTER ROOM 114 UNTIL ABSOLUTELY NECESSARY. A HEALTH PHYSICS' SURVEY IS VITAL PRIOR TO ENTRY.
- 8. Identify the leaking or ruptured fuel element. The fuel element which ]
is leaking fission products must be accurately identified and placed in safe storage before the remaining intact elements may be utilized.
This will be accomplished in the following manner:
- a. Have the Health Physics ersonnel move the portable gaseous and particulate monitors to the reactor bridge for continuous monitoring. Health Physics personnel will be present.
- b. Move each element from the core to the "X" or "Y" bas 5.et.
- c. Draw a grab sample from above each element and give to the ]
laboratory group for analysis. If one of these samples indicates fission products present, this element will be inspected first.
- d. Move the fuel element from one of the baskets to the fuel inspection rig for visual inspection.
- e. The Reactor Manager will determine the disposition of the leaking fuel element (s).
Rev. 5/02/89 App'd % REP-20-2 l
o
REP-21 HIGH STACK MONITOR INDICATIONS In the event of High Stack Monitor readings (Gas, Particulate or Iodine in excess of alarm points):
IMMEDIATE ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Contact the Health Physics office during normal working hours.
I After hours, contact: HEALTH PHYSICS CALL LIST.
Evaluate the extent of iodine and particulate levels with overlay I, and
- 3. .
I If the extent of radioactivity is great enough to gas with overlay II.
enter event classifications, the highest category of event indicated by gas,' iodine or particulate reading will be used to classify the event.
SUBSEQUENT ACTIONS:
- 1. IODINE AND PARTICULATE (overlay I)
Check the stack monitor reading with overlay I. The ranges of values I represented on the overlay are the threshold levels of concentrations cor-responding to specific emergency events in excess of Technical Specification limits.
The overlay thresholds assume the present release rate will be constant for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. They are conservative, since the present release rate may exist for less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the emergency action levels are:
UNUSUAL EVENTS - 3800 MPC average over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l ALERT EVENTS - 19000 MPC average over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SITE AREA EMERGENCY - 95000 MPC average over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (i.e., for UNUSUAL EVENT + could have 91,200 MPC for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> = 3800 MPC x 24 hrs; therefore still have 3d00 MPC average over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)
These overlays are to graphically assist the operator's judgement as to the extent of release. ;
Orig.- 7/03/85 App'd OW\ REP-21-1 L_-____ _ _ _ i
I
- 2. GAS (overlay II)
T 66 x 104 CPM (19,000 MPC), and remains between these levels for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ]
with no evidence of declining, the event shall be classified as an UNUSUAL EVENT.
, E b. IF gas concentration exceeds 1.66 x 104 CPM (19,000 MPC) but less than ]
E D x 104 CPM (95,000 MPC) and remains between these levels for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ]
with no evidence of declining, the event shall be classified as an ALERT.
T x 106 (FULL SCALE) and remains between these levels for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with I no evidence of declining, the event shall be classified as a SITE AREA EMERGENCY.
IF gas concentration reaches full scale and remains there for 10 minutes I d.
iTithout decline and cannot be attributed to electronic failure, the event shall be class,1fied as SITE AREA EMERGENCY.
- e. IF gas concentration shows no signs of leveling off or declining, ifetermine a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average concentration each 30 minutes by using the formula:
= AVE 30 MIN READING (CPM)
CPM 24 HOUR AVE 48 Use this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average to determine the event classification.
NOTE: A GENERAL FORMULA FOR DETERMINING 24 HOUR AVERAGE CONCENTRATIONS IS AS FOLLOWS. ANY APPROPRIATE TIME INTERVAL CAN BE USED BUT MUST BE EXPRESSED IN MINUTES.
AVE INTERVAL READING INTERVAL TIME DURATION (MIN)
= (in CPM) x 60 (MIN /HR)
CPM 24 HOUR AVE 24 HOURS or simplified CPM 24 HOUR AVERAGE
- AVE INTERVAL READING (CPM) x INTERVAL TIME DURATION (MIN) 1440 I
ev. 5/02/89 App'd REP-21-2 I
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s REP '- -
BOMB OR OTHER OVERT THREATS
- Upon any ' direct threat or actions by any person _or group of persons which may endanger personnel ' safety or the safe operation of the reactor, the DUTY '
OPERATOR'shall:
IMMEDIATE ACTIONS:
- 1. Immediately shutdown the reactor-and secure the master control' switch.
- 2. Notify.the Shift' Supervisor.
- 3. Insure all' doors' are secured, with priority. to the truck entry door and personnel airlock door.
- 4. Notify the University police by telephone.
- 5. ' Facility evacuation or. partial evacuation may be used to remove persons
~
from affected areas.
NOTE: FACILITY STAFF'SHOULD NOT ENTER ANY DIRECT CONFLICT EXCEPT WHEN NECESSARY FOR THEIR PERSONAL SAFETY.
1 Orig. . 7/03/85 App'd kb REP-22-1 i
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APPENDIX A
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i 11
DATE:
BEACTORSTARTUPCHECKSHEET K ULL POWER OPERATIOi; TIME (Startec): ]
BU1LD1NG AND MECHAt[lCAL EQUIPMENT CHECKLIST E -l 1. Emergency air compressor (load test for 30 minutes after maintenance day). ]
3 2. Beamport Floor:
I a. Beamport radiation shielding (as required). ]
d b. Unused beamports checked flooded (af ter maintenance day). ]
E c. Seal trench low level alarm tested (after maintenance day). ]
7 , 3. a. Check operation of fan failure buzzer and warning light. (Required if ]
shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.) ]
Test stack monitor and low flow alarm per 50P while in west tower. ]
E b.
,M 4. Check the EG governor oil level and check local mode switch in remote. (After ]
maintenance day. If shutdown for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, run EG for 30 minutes.) ].
E 5. Emergency pool fill. (Check valves PIV-1 and PlV-2 locked open.) ]
E 6. Visual check of CT and secondary equipment: ]
I a. Oil level in CT f ans normal (after maintenance day). ]
mi b. Secondary makeup isolation valve power switch closed, valve cycled to ]
verify operation and placed in auto mode. ]
- 7. Visual check of room 114 equipment: )
.J a. P501A and P501B coolant water valves open. ]
- b. Pumo controllers unlocked to start (as required). ]
IE"I c. Check valves 599A and 599B open.
- d. Air valve for valvt operating header (V0P31) open.
]
]
I E e. Ng back-up valve open. ]
IE f. Alr/N2 cross connect valve open. ]
l g. 51 and S2 hydraulic pumps on (oil level normal). ]
- h. Valves 51 and S2 cycled in manual mode and positioned as required. ]
- i. Vent the pool hold-up tank. ]
J. Vent the pool skimmer system pump. ]
- k. Check pipe trench free of water (after maintenance day, check the ]
four-pipe annulus drain valves for water leakage). ]
- 1. Add DI water to beamport and pool overflow loop seals. ]
- n. Check oil reservoir for pumps 501A, 501B, and 533 for adequate supply. ]
Add if necessary. ]
[ } m. Visually check room 114 and DI area after all systems are in operation. ]
- 8. Reactor Pool:
- a. Reflector experimental loadings verified and secured for start-up.
- b. Flux trap experimental loading verified and secured for start-up, or strainer in place.
l I c. Check power on and reset, as necessary, silicon integrator, totalizer setting, silicon rotator and alarm system.
fREACTORCONTROLSYSTEMCHECKLIST All chart drives on; charts timed and dated. IRM recorder to slow.
1.
j p
2.
3.
Fan failure warning system cleared.
Annunciator board energized; horn off.
- 4. Television receiver on.
- 6. Secondary system on line per 50P (as needed).
f 7. Primary system on line per SOP: I
- a. Primary cleanup system on line.
- 8. Pool system on line per SOP:
I a. Pool cleanup system on line. ]
- b. Pool reflector oP trips set as required. ]
f 9. Nuclear Instrumentation check completed per SOP:
- a. The following trip values were obtained during the check:
IRM-2, run-in seconds (11+1) Scram seconds (9+1) f IRM-3, run-in WRM-4, run-in PRM-5, run-in PRM-6, run-in seconds (1171)
% (114+1) -
% (11471)
Scram Scram Scram Scram seconds (971)
% (119+1) ~
% (11971)
% (114_T1) %(11911) iRev.5/02/89 App'd M SOP /A-la
' REACTOR STARTUP CHECKSHEET FULL POWER OPERATION (cont 'd ) Page;
- 10. Channel 4, 5, and 6 pots returned to latt heat balance position.
i.
E
- 11. SRM-1 detector response checked and set to indicate > 1 cps.
l 12. Check of process radiation monitors (front panel checks):
- a. Fission product monitor,
- b. Secondary coolant monitor.
NOTE: . Items 13 through 34 are to be completed in sequence immediately prior to j pulling rods for a reactor startup. i
- 13. Annunciator tested.
- 14. Annunciator alarm cleared or noted.
- 15. Power selector switch 158 in position required.
- 16. a. Bypass switches 2540 and 2S41 in position required.
- b. All keys removed fron bypass switches.
~
- 17. Master switch 151 in "tm position.
- 18. Magnet current switch on, check " Reactor On" lights.
- 19. Reactor isolation, facility evacuation and ARMS checks (after maintenance day).,
These items are to be checked with scrams and rod run, ins reset, and when i appropriate items are actuated, verify that the TAA's do trip. i
- a. Reactor isolation switch (leave valves and doors closed) (after maint. day)4
- b. Facility evacuation switch (check outer containment horns) (after maint. dej
- c. ARMS trip setpoints. checked end tripped, check buzzer operational locally j for all channels and remotely for channels 1 through 4 and 9.
Channel 1 - Beam Room South Wall Channel 2 - Beam Roma West Wall Channel 3 - Beam Rom North Wall Channel 4 - Fuel Storage Vault Channel 6 - Cooling Equipment Room 114 Channel 7 - Building Exhaust Air Plenum (after maintenance day).
Channel 8 - Reactor Bridge (switch in " Normal") (after maintenance day).
Channel 9 - Reactor Bridge backup (switch in " upscale") (after maint, day).:
- d. Check HV reedings: volts. (520 + 10: VDC)
- e. Check 150V reading: ~ volts. (150 VDC +20)
( - 5)
- f. Selector switch on ARMS in position 5.
- g. Trip backup monitor with attached source (after maintenance day).
- h. Reactor isolation horns switch in " Isolation Horns On" position.
Valves and doors open.
- i. All ARMS trips set per 50P.
- j. Check ventilation fans, containment and backup doors.
- 20. Operate reg blade from full-out to full-in and set at 10" + .05".
- a. Check rod run-in function at 10% withdrawn and annunciator at rod bottomed.
- 21. Raise blade A to 2" and manually scram.
- 22. Raise blade 3 to 2" and trip manual rod run-in.
- 23. Raise blade C to 2" and scram by WRM trip.
- 25. Annunciator board energized; horn on.
- 26. Jumper and tag log cleared cr updated.
- 27. IRM recorder in fast speed.
- 28. Check magnet current for 90 ma on each magnet.
- 29. Cycle WRM range switch.
- 30. Reset " white rat" scram monitor.
- 31. Estimated critical blade position (corrected): _
inches.
- 32. Pre-startup process data taken.
- 33. Routine patrol completed.
- 34. All reactor and license related systems upon which maintenance was performed have been reviewed and are operable.
F i 35. Reactor ready for startup.
Time (Completed)
Shift Supervisor / Lead Senior Operator App'd M rM SOP /Ac L_Rev.5/02/89 _ _ - _ - _ _ _ _ _ _ _ _ - _ _ - _ _ _ - - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
DEVIATION FROM ]
STANDARD OPERATING PROCEDURE ]
- 1. Section of SDP where deviation applies:
- 2. bason for deviation from SOP: ]
] l
]
]
3 J
Submitted by: ]
]
Shift bupervisor or Lead Senior Operator ]
Reviewed by: ]
]
Operations Engineer / Reactor Manager ]
l~_l Reviewed by Reactor Procedures Review Subcommittee (RPRS) ]
3 Date Initials ]
Disposition recommended by RPRS: ]
l-l S0P Revisivn Required ] ;
l_l S0P Revision Not Required ]
Rev. 5/02/89 gpp.d dW SOP /A-2a ]
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NOTE: THIS PAGE INTENTIONALLY LEFT BLANK 1 l
1 Rev. 5/02/89 App'd i1}fhw SOP /A-2b ]
1'
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Date REACTOR SHORT-FORM PRE-CRITICAL CHECKSHEET
- 1. Front panel check of SRM completed.
- 2. SRM recorder and scaler on.
- 3. Front panel check of IRM #2 completed.
- 4. IRM #2 trip values Run-in sec.
Scram sec.
- 5. Front panel check of IRM #3 completed.
- 6. IRM #3 trip values Run-in sec.
Scram sec.
- 7. Front panel check of WRM completed.
- 8. WRM trip values Run-in %
Scram %
- 9. Front panel check of PRM Ch. #5 completed -
SEE NOTE 1.
]
- 10. PRM #5 trip values Run-in %
Scram %
- 11. Front panel check of PRM Ch. #6 completed -
SEE NOTE 1. ]
- 12. PRM #6 trip values Run-in %
Scram %
- 13. IRM recorder to fast speed.
- 14. Cycle WRM switch.
- 15. Pred'.cted critical position ( in.).
- 16. Reset scram and run-in circuits.
- 17. Pool and experiments checked and ready for startup. _
- 18. Reactor ready for startup.
NOTE 1: Pot returned to position obtained from heat balance.
P,ev . 5/02/89 App'd N @ S0P/A-3a
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NOTE: THIS PAGE INTENTIONALLY LEFT BLANK i
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Rev. 6/80 App'd M SOP /A-3b
1 REACTOR SHUTDOWN CHECKSHEET l
^
DATE
- 1. Time of reactor shutdown: ,.
- 2. All blades bottomed and drive mechanism full in.
1
- 3. Magnet current switch off. l
- 4. SRM set to required position (= 1000 counts if refueling).
- 5. Reactor primary system shutdown per S0P IV.
i
- 6. Pool system shutdown per S0P V. I 1
- 7. Secondary system shutdown per 50P VI.
- 8. Cooling tower fans off.
- 9. Digital readout switch off.
- 10. Annunciator board on off .
- 11. Reverse osmosis unit to standby.
- 12. Sample inventory satisf actory and data sheets updated.
- 13. Si integrators recorded.
- 14. All bypass switches off and keys in key box.
- 15. Master switch off on .
- 16. DCT system secured.
- 17. Room 114 check:
- a. Cooling flow to P501 A/B secured.
- b. Valves Si and S2 hydraulic motor off.
- c. N2 system and air to valve header secured.
- d. Calgon units secured.
- e. Room 114 pump controllers locked out.
- 18. Completed and logged Reactor Shutdown Checksheet.
Shift Supervisor / Lead Senior Operator ]
Rev. 5/02/89 App'd M S0P/A-4a
.I l
4 -REACT 0Pc SHUTDOWN CHECKSHEET (cont'd)'
BUILDING SHUTDOWN CHECKS lHEET- i
- 1. - Pool' level ~ normal . )
' . 2. .. ARM trip levels set ~per 50P. l i
3.: ' Annunciator board off.
~
~
- 4. TV-unit secured.
5.: ARM and off_-gas recorder paper supply okay, charts timed and dated.- f j
- 6. --- Primary / pool , drain collection system secured per SOP.
- 7. . Routine patrol . completed._
e 8. .SRM, IRM, WRM, PRM, ARM and process radiation monitors in operate mode.
- 9. Master. key switch off and in key box. !
'10. . Test of containment intrusion alarm completed.
~
System energized.-
~ 11. All keys accounted 'for.
12._ Building shutdown and reactor secured.
- 13. Control room doors locked.
- 14. Completed building shutdown checksheet,-
- 15. Logbook entries complete, crews signed out.
Shift Supervisor / Lead Senior Operator
,?
i-Rev. 5/02/89 App'd id W SOP /i.-4b
Date:
NUCLEAR DATA Rod Position Nuclear Instrumentation Power by Heat i Time Averaae Channel Channel Channel Channel ~ Cnannel i Cnannel Bal ance in M',,'
I 3 4 5 6 Primary / Secondary RR GR 1 2
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I I
I I
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I I
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Rev. 5/74 App'd W DTW SOP /A-5a (Retyped only 7/30/85)
Mode PROCESS 0 Date.
~~
i I I ! I i : !
I l .
! I Time l l l l l l l 1 i I I i !
In ' Pool Ht. Exch. l l l Pressurizer Level I I I Pool Refl . 4P L l l l
PS 944A I l PS 944B DPS 928A DPS 928B l l l DPS 929 l l Sec* Th (6)
Sec. le (5)
Sec. AT l l Sec. Water Flow l l Pool Ic Loop A (3)
Pool Ic Loop B (4)
Sec. Th Pool A (7)
Sec. Th Pri. A (8)
Rx Cond In Rx Cond Out Pool Cond in Pool Cond Out Stack Gas Stack Part. l l Stack Iodine l =
Operator Reader Heat Balance By Manual Calculation: ,
PROCESS DATA Moce Date l l l l 1 I I I I Time I I I l I i l I I I I I Pri. Flow A l l l I l i l l I I I I I
,P ri . . Fl ow .B l l l l l l } l ,
Pool Flow A Pool Flow B Demin Flow A l
Demin F1ow B i _
Pri. I c Pri, ih Pri. AT !
Pool I c Pool Th
- Pool AT l South Wall ARMS iWest Wall ARMS l North Wall ARMS I
Fuel Storage ARMS ,
Room 114 ARMS ,
Bldg. Air Exh ARMS Rx. Bridge ARMS Fission Product
~
Sec Water TAA Yellow j r
'TAA Rod Run-In -
l TAA Green l l
) l Rx Pressure Rx TcLOOP A Rx Tc LOOP B ..m. ..
.a um o
_ _ _ _ _ . _ _ _ __.____.______._..__.__.A ___.___________________._____m__._._ _._ _._._____ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ . _ _ _ _
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NOTE: THIS PAGE INTENTIONALLY LEFT BLANK I
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I Rev. 6/80 App'd NM SOP /A-
l
' CORE: STAPTUP NUCLEAR DATA Date:
TIME P05. P05. P05. SRM-1 1 IRM-2 IRM-3 i WRM 4 PROCEEDINGS!l
~~
Critical Rod Position A B C D RR ECP Power at Critical Position Pri . Temp. / Pool Temp. /
Operator / Remarks:
CORE: Date:
APP. BANK RR SRM TIME P05. P0S. POS. SRM-1 IRM-2 IRM-3 WRM-4 PROCEEDINGS Critical Rod Position A B C D RR ECP Power at Critical Position Pri . Temp. / Pool Temp. /
Operator / Remarks:
~~
CORE: Date:
APP. BANK RR SRM TIME POS. P05. P0S. SRM-1 IRM-2 IRM-3 WRM-4 PROCEEDINGS l
\
I Critical Rod Position A B C D RR ECP j Power at Critical Position Pri. Temp. / Pool Temp. / l Operator / Remarks:
Rev. 3/9/83 App'd b/GMV\ SOP /A-6a
ICore Startup Pot 5ct: 15s 4 5 6 MWD Last Sheet
~ ~ ~ ^" ~~
MWD Tnis Sheet ~
Pot Changes Total MWD Date Time Channel Settina
~
Fuel Element Record
~
d Core Position Fuel Element MWD to Date 1 MO- ~~
2 MO-3 MO-4 MO- ~
5 MO-6 MO-7 MO-8 MO-Power Date Time Time Time Time at Tnis Level Arrival Departure Hrs Min Pwr Level (days) MWD Comments Rev. 5/02/89 App'd th SOP /A5
' Sheet No: Date: ,
PNEUMATIC TUBE IRRADIAT10N5 Run Glock lime Total Project Room Irradiation No. In out Name No. Runs No. No. Min. Sec. File No.
1 2
3 4
5 6
7 8
9 10 11 12 13 li.
15 16 17 18 19 20 21 l 22 23 24 25 26 27 28 29 30 ,
31 32 33 34 Rev. 9/19/83 App'd (M@ SOP /A-7a
l NOTE: THIS PAGE INTENTIONALLY LEFT BLANK Rev.- 6/80 App'd 1,% SOP /A-7b
REACTOR ROUTINE PATROL Date:
1
~1. Time of start of patrol .
1 I2. Time and date all charts
- 3. Check ARMS trip settings
- 4. Visual check of entire pool
- 5. Anti-siphon tank pressure 36 psig 1 3 psi 1 6. North iso door seal pressure 18-28 psig
- 7. South iso door seal pressure 18-28 psig 5th level backup doors
- 8. Open 4
- 9. 5th level detector reading 0-3.5 mr/hr
- 10. 5th level trip point set 3.5~mr/hr It
- 11. 16" iso. viv A air pressure 45-55 psig
- 12. - 16" iso viv B air pressure > 90 psig Emerg compress on standby c open,
- 13. egsed 1
- 15. Door 101 seal pressure 18-28 psig
- 16. BP floor Conditions normal.
Fuel vault
- 17. Locked
- 18. Inner airlock door seal press. 18-28 psig i 19. Outer airlock door seal press. 18-28 psig
- 20. Cold deck temperature 51 2 4 F
- 21. T-300 level > 2000 gal .
,i E2. T-301 level < 6000 gal.
- 23. Labyrinth sump Level < Alarm Pt.
On the first routine patrol of the day or the first patrol af ter a startup, drain all water from the anti-siphon systic. scaining causes the pressure to drop significantly, return to the middle of the band (36 psig) and record the pressure here. If a condition or reading is normal, enter a "/" (for conditions) or the reading in the applicable box. If the con-dition is abnormal, enter the condition or reading and circle it. Explain all abnormal con-ditions or readings in the REMARKS on page 3.
Rev. 5/02/89 App'd id}YTY\ SOP /A-Ba
DATE:
REACTOR ROUTINE PATROL (cont'd)
- 24. R0 unit power .
0N 24-28 C or Standby Ei h
- 25. RO unit temperature
- 26. R0 unit pressure 190-200 psig or standby Ef
- 27. EG Rm. ,btb@cheswit hSun mids. Thermostat > 50 F f to Auto Temp > 40*F (Gas i sight glass )
- 28. T-300, 301 Room Aarmnstat,>55F g 4termostat) 40 F E
- 29. Rm.114 particulate filter & < 2.5" H 2O
- 30. External doors fhenSe$$ndu$h
- 31. CT basin water level 5-10" <
- 32. Automatic secondary makeup valve Open/ Auto (genating) I
- 33. Acid day tank level Visible g Operable
- 35. P-punp(s) running
- 36. Pump strainer & 0-7.0 psi
- 37. Discharge pressure
- 38. Pump strainer & 0-7.0 psi g 1
- 39. Discharge pressure
- 41. WT booster fan Running E
- 42. Acid control and pH o 0 8 m E.
- 43. Blowdown control /cond. /m how50g8 g
- 44. Fission product monitor flow ,95-105 cc/ min j
- 46. Pressurizer N supply press90-100 psig g 2
- 47. Check rm. 114 from door. Ef 48 Deltech oil filter " red level" < 75% dark red .
and blowdown .
- 49. Seal trench 6'
$~n Rev. 5/02/89 App'd dW\ SOP /A-8
DATE:
ZACTOR ROUTINE PATROL (cont'd)
- 50. Full N 2bottles Total > 3 ]
iS1. Bank A bottle pressure > 250 psig ]
- 52. Bank B bottle pressure > 250 psig - ]
- 53. Bank on service A or B ]
l54. N header pressure 135-145 psi ]
2 iSS. Waste tank #3 level ]
]
l56. Waste tank #2 level
- 57. Waste tank #1 level .
]
l58 Doors to Ct, WT's, Demin. Locked ]
Rm. 114 and CT Tunnel
]
159. Time of completion of patrol
- 60. Operator initials ]
REMARKS:
P.e v .
5/02/89 App'd hM SOP /A-8c
1 1
1
,i NOTE: THIS PAGE INTENTIONALLY LEFT BLANK 1
I I
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Rev. 5/02/89 App'd NM SOP /A-8d ]
i I
UNSCHEDULED REDUCTION IN POWER REPORT NO.
]
- NOTE: PLACE THIS NUMBEP., DATE, AND TIME ON ALL PROCESS & NUCLEAR INSTRUNMENT CHARTS ]
.DATE:
TIME OF SCRAM / ROD RUN-IN (circle one) ]
I POWER LEVEL AT TIME OF POWER REDUCTION:
W KW MW W ]
MAXIMUM POWER ACHIEVED: KW ]
MW ]
INDICATION OBSERVED ON ANNUNCIATOR AND/0R OTHER INSTRUMENTATION. (Indicate if tne ]
reactor was subcritical when power reduction occurred; indicate maximum AT on ]
I in-pool heat exchanger for loss of flow / loss of electrical power.) ]
I CAUSE OF REDUCTION IN POWER. (If scram or RRI is spurious, document power levels and ]
relevant process information to show no actual power transients occurred.) ]
I :
CORRECTIVE ACTION TAKEN TO ALLEVIATE CAUSE OF POWER REDUCTION. ]
I I
PERMISSION TO TAKE THE REACTOR CRITICAL RECEIVED FROM:
l TIME REQUIRED TO BRING REACTOR BACK TO PREVIOUS POWER LEVEL:
Form filled out by:
Form reviewed by:
REMARKS:
I Rev. 5/02/89 App'dh SOP /A-9a
I NOTE: THIS PAGE INTENTIONALLY LEFT BLANK I'
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Rev. 6/80 App'd idM SOP /A-9b I;
RADIATION WORK PERMIT RWP No.: Date: Time: Location:
Work
Description:
/ e k
e .~ w
. . . i.
RWP expires 24 ho from above .J.4. *n, E date and time unl s extended to:? DATE TIME ISiGNED %
.. w . -- p ic.st.+;m.
p . y -c.-.-... . n. -
R ADI ATIONSURVE'Y RESULTS: PR OTECTIVE EOD'IP' MENT HEOUIRED:
+ a ~m. .-:::. + .t :';. .
Genera rea: mrem /hr _ S. Dos..R :-5 "- ~ Finger Rings
+., .
Hot eas: ._ b Coats .
Coveralls I
mrem /hr at 7 Gloves: Latex. _ Rubber
..- . . , . . c -
' '# ~
'n rem /hr at f_1 M - i '
L _ .1 .
f .
Shoe Covers: ;. . _ Nylon Rubber _ Boots mrem /hr at '
I- :
Reso. Ewipment:
CONTAMINATION SURVEY RESULTS:
Half Face Full Face General Area: dpm/100 cm
% #._ Other Other Areas: . .. .
- 2-'
~
M. ,-
- d m/100 cm2 .
...; u .. . , .
t .
m/100U.n2-
-i..,.a n:i d:4 ; - c1 r:. .
- .s:+>s.; .T:p q_-y +a=u.
. =:.=....~...
- 3.;e " . . .sm' :;--:. 7. . . .
Continuous H.P. Monitoring.. 2 .H;f . , : 1.- Intermittent H.P. Monitoring
.;m :a .
REQUIRED PRECAUTIONS: .- '... "M
..-- Q WE52x @aiE
.c.,- y.>,<..
.,~-
v -- ,. w y .:... -
Tool & Equipment Survey opitffitrdiPost' Area H & F Count On Leaving Job Personal Survey on Leaving Job Air Monitoring Special Time Sose Limit Operation Shitt Supervisor Read For Information:
S4gned Date ,
APPROVALS:
H.P. Summary Report? Yes No Health Physics Date Teme if yes, attach copy to this RWP.
. ion superv,,o, o.te 7,me
\
Rev. 10/8/86 App'd WM\ 50P/ A-10a
.. r .
I 4ECI AL INSTRUCTIONS:
I 7ERSONNE L INVOLVED: Total Total g Est. Est. g Dose Dose
- 1) mrem 13) mrem
- 2) mrem 14) mrem
- 3) mrem 15) mrem 4), mrem 16) mrem .
- 5) mrem 17) mrem
- 6) , mrem 18) mrem
- 7) mrem 19) mrem
- 8) mrem 20) mrem
- 9) mrem 21) mrem
- 10) mrem 22) mrem
- 11) mrem 23) mrem mrem mrem
- 12) 24)
I H.P. COMME NTS I
I l
1 Signed Date s s - n 6t/Af 6) // /A _ il fah
RETURN ORIGINAL TO HEALTH PHYSICS OFFICE No.
WASTE TANK SAMPLE REPORT TANK NO. TANK LEVEL (Liters)
Completed adding water to this tank. TIME DATE S TIME DATE IAMPLER 1. Analysis Results Nuclide Half Life Physical Form Concentration MPC Acti vity I a. H-3 12.3Y _
(uCi/ml)
( uCi i I
I I
I O
pH FRACTION OF MPC I Analysis by TIME DATE Concentration (uCi/m) Total Volume (liters) Activity (mci) x =
(a)
(b) x -
- 2. Approvals Required for:
Any Discharge ......................
Shift Supervisor Discharge of > 10 mci of H 3 , > 2 mci of other activity, or I to Secondary System .................. I Reactor Manager l Di scharge Limit Approved . . . . . . . . . . . . . . . . .
Health Physics {
1
- 3. Action Taken Date Discharged Time Discharged Volume Discharged (Liters)
Tank Discharged to (check one) Sanitary Sewer Secondary System Not Discharged 1
REMARKS l 1
i Rev. 10/8/86 App'd 1 AJDM SOP /A-lla I
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I Rev. 12/15/82 App'd Gk 30P/A-11b II
I ,
Date ,
PRIMARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET This checksheet shall be completed when required by the SOP. The operator performing the check will verify the position of each valve and indicate the verification by initialling the checksheet. Under the direction of the Shift Supervisor, a valve may be positioned other than noted on this sheet. The operator will check the valve to be in the desired position, line out the normal position on this sheet, and write in the actual position of the valve. The reason for the valve beitig positioned abnormally will be noted in the COMMENTS section.
L Throttled valves shall be checked to be in the position shown by the tag on the valve.
Note the valve's position in the space prcvided on the checksheet.
Valve # Valve Description Position <
Vent tank regulator valves Zero pressure I 1.
2.
551 518AM Vent tank vent Open
- 3. 518AL Vent tank air supply Closed I 4. 598B Air supply to 543 A & B Open ]
- 5. 598A Air supply to 546 Open ]
- 6. 5185 Loop drain (in tunnel) Closed (locked)
- 7. SIST Loop drain (in tunnel) Closed (1ocked)
- 8. 5180 TH vent and FPM cutout Open (locked)
- 9. 595L Isolation valve for DPS-929 Open l
- 10. 568H DPS-929 inlet / outlet test vlvs equaliz. Closed
- 11. 595M Isolation valve for PS-944A Open
- 12. 595N Isolation valve for DPS-929 & PS-944B Open
, 13 . 595B Return valve from FPM Open (locked)
- 14. 518X Tg vent valve Closed (locked)
- 15. 510A P-501A suction Open
- 16. 510D P-501B suction Open
- 17. 518A P-501A gage cutout Open
- 18. 518AH P-501B gage cutout Open
- 19. 518B P-501A gage cutout Open
- 20. 518AB P-501B gage cutout Open
- 21. 538A F-501A bypass Throttled (locked)
(No. turns open )
- 22. 538B P-501B byass Throttled (locked)
(No. turns open )
- 23. 510C P-501A discharge Open Rev. 5/02/89 App'd hfWh SOP /A-12a ]
I
_ 4
PR8 MARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET (cont'd)
Valve # Valve Description Position
- 24. 510E P-501B discharge Open
._ 25. 518P Tg vent Closed (locked) 26.
27.
510B 510F HX inlet to 503A HX inlet to 503B Open Open l
28.- 515A HX drain for 503A Closed (locked)
- 29. 5681 DPS-928A inlet / outlet test vivs equaliz. Closed
. _ 31. 595C HX 503A DPS outlet Open
- 32. 515Y HX drain for 503B Closed (locked)
- 34. 595E g
~
- 35. 568J DPS-928B inlet / outlet test vivs equaliz. Closed 5 i
- 36. 540A HX outlet for 503A Throttled (locked)
(No. turns open )
- 37. 540B HX outlet for 503B Throttled (locked)
(No. turns open )
- 38. 5991 PT 943 cutout Open (locked)
- 39. 518Y TC vent Closed (locked)
- 40. 595A Inlet to FPM Open (locked)
- 41. 518M HUT vent Closed
- 42. 518L HUT vent Closed (locked)
- 43. 515K HUT drain Closed (locked) E
- 45. 568B FE 913B valve manifcid Inlet /outiet open;
- 46. 518AE HX 503A loop strainer drain Closed
- 47. 518AF HX 503B loop strainer drain Closed
- 48. 518AA HX 503A vent Closed (locked)
- 49. 518AI HX 503B vent Closed (locked)
- 50. 528 P-533 recirc. to T-300 Cl osed
- 51. 515J 5 513A suction Open
- 52. 518E P-513A suction gage cutout Open
- 53. 518F P-513A discharge gage cutout Open
- 54. 515L P-513A discharge Open '
- 55. 515W P-513A bypass Cl osed Rev. 5/02/89 App'd A SOP /A-12b $
Reset EI J
i PRIMARY SYSTEM NORMAL OPERATION VALVE LINEUP CHECKSHEET (cont'd)
Valve # Valve Description Position
- 57. 595H Primary sample valve Open
- 58. 515U V-527A cutout valve Open
- 59. 515AA Press drain to drain collection system. Open
- 60. 515B V-527C cutout valve Open
- 61. 515S V-5270 cutout valve Open (locked) l
- 62. 544 V-545 cutout valve Open
- 63. 599G PZR local level indicator cut Mt Closed (locked)
- 64. 599H PZR local level indicator cutout Closed
- 65. 515AB Pressurizer drain to waste system. Closed
- 66. 515C P-533 suction Open (locked)
- 67. 599A PS-938 cutcut Open
- 68. 599B PS-939 cutout Open 599C PS-940 cutout Open
_ __ 69.
- 70. 599D PS-941 cutout Open
- 71. 599E PS-945 cutout Open
- 72. 599F PS-946 cutout Open
- 73. 599N FE-913A drain Closed
- 74. 5990 FE-913A drain Closed
- 75. 599V FE-913B drain Closed
- 76. 599W FE-913B drain Closed COMMENTS:
Rev. 5/02/89 App'd NA 50P/A-12c ]
Reset
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I Rev. 5/02/89 App'd hm SOP /A-12d .,
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'f,',,
jNOTE: PLEASE RETURN TO HEALTH PHYSICS OFFICE AND ATTACH TO INDICATED ANALYSIS. SHEET.
SECONDARY WATER ACTIVITY. ANALYSIS-
- Date: Wt. Analysis Number:
"~
(from Wt. sample sheet)
- Ti~me :-
'Initie?s:
Sample Taken from Tower' Sumo _-
Isotope' Half Life Activity 3
H- 12.3 yr Si/ml Analysis performed by.:
Time Date:
Tritium activity is less than 10-4 41/mi and all other activities are within 10 CFR 20 limits for discharge to the sanitary rewer. Approval is given to turn on the blow-down' system.
~
Shift 5' 61rvisor/ Lead Senior Operator ].
Blowdown'on Time Date Initials Rev.-5/02/89 App'd (L$M SOP /A-13a ]
s i
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Rev. 5/02/89 App'd d h N SOP /A-13b ]
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Date POOL SYSTEM VALVE LINEUP CHECKSHEET ]
This checksheet shall be completed when required by the S0P. The operator performing the check will verify the position of each valve and indicate the verification by initialling the checksheet. Under the direction of the Shift Supervisor, a valve may be positioned other than noted on this sheet. The operator will check the valve to be in the desired position, line out the normal position on this sheet, and write in the actual position of the valve. The reason for the valve being positioned abnormally will be noted in the COMMENTS section.
Throttled valves shall be checked to be in the position shown by the tag on the valve.
Note the valve's position in the space provided on the checksheet.
Valve # Valve Description Position
- 1. 598A Air supply to 546 Open ]
- 2. 555P Air supply valve to V-547 Closed
- 3. P-532 pool suction Open I 4.
548A 548B P-532 pool (at refuel) suction Cl osed
- 5. 518U Vent valve (pool TH) Closed (locked) 6, 515X P-513B bypass Closed
- 7. 515N P-513B discharge Open
- 8. 518H P-513B suction gage cutout Open
- 9. 518G P-513B discharge gage cutout Open J
, 10. 522C Pool drain / fill Clored (locked)
- 11. 522B Pool fill Closed (locked)
- 12. 5150 Cleanup return to loop Closed (locked)
- 13. 515M Cleanup suction from pool Closed (locked)
- 14. 515T Cleanup suction from loop Open
- 15. 522F P-508A discharge Open
- 16. 522E P-508B discharge Open I 17. 531B P-508B bypass Closed
__ _ __ 18 . 5101 P-508A gage cutout Open
- 19. 518J P-508A gage cutout Open
- 20. 518AD P-508B gage cutout Open
- 21. 518AC P-508B gage cutout Open
- 22. 599J PS-947 cutout Open (locked) l 23.
24.
539A 539C P-508A suction P-508B suction Open (locked)
Open (locked)
Rev. 5/02/89 App'd _k SOP /A-14a ]
POOL SYSTEM VALVE LINEUP CHECK 5HEET (cont'd)
V61ve # Valve Description Position
- 25. 518V Vent valve Closed (locked)
- 26. 515P Cleanup return to pool Open HUT outlet Open
- 27. '514B 28.
29.
539B 539D HX-521A.iniet HX-521B inlet Open Open l
- 30. 522A HX-521A outlet Throttled (locked)
- 31. 522D HX-521B outlet Throttled (locked)
- 32. 518N HUT vent cutout Open
- 33. 518K HUT vent Closed (1ocked)
- 34. 515P. HUT drain Closed (locked)
- 35. 5150 HX-521A drain Closed (locked)
- 36. 515Z HX-521B drain Closed (locked)
- 37. 518W vent valve Closed (locked)
_ 38. 518AG Pool system "Y" strainer drain Closed
- 39. 518Q Drain valve (tunnel) Closed (locked)
- 40. 518R Drain valve (tunnel) Closed (locked)
- 41. 514A V-509 cutout Open (locked)
- 42. 568G PT-917 cutout valve Open
- 43. 599Z PT-917 vent Cl osed
- 44. 599Y P-532 suction vent Auto Float
- 45. 5151 P-532 suction Open g 46, 518D P-532 gage cutout Open E
- 47. 518C P-532 gage cutout Open
- 48. 515E Skimmer filter inlet Open
- 49. 515D Skimmer filter outlet Open
- 50. 567A Drain collection pump suction Open
- 51. 567B Drain collection pump suction drain Closed l l
- 52. 566 Drain collection system discharge Open i 53. 567C Drain coll sys disch to 513B suction Open
- 54. 593 Skimmer suction T-300/T-301 Open
- 55. 518AJ/AK HX-521 A/B loop vents Closed (locked)
I' Rev. 5/02/89 App'd DtA SOP /A-14b Reset I
l
1.
l.
POOL SYSTEM VALVE LINEUP CHECKSHEET (cont'd)
Valve # Valve Description Position
- 58. 5995 FT-912D drain Closed
- 59. 599T FT-9120 drain Closed
- 60. 599M FT-912F drain Cl osed
- 61. 599Q FT-912F drain Closed
- 63. 595J Pool cleanup effl. to sample station Open
- 64. 595G Pool influent to sample station Open
- 65. 595K Pool cleanup vent Closed
- 66. 515AC Pool cleanup to blank flange Closed COMMENTS:
Operator Rev. 5/02/89. App'd EM S0P/A-14c ]
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Rev. 5/02/89 App'd Nh S0P/A-14d Reset
I MURR P0OL WATER ANALYSIS
, Sample drawn:
Date: Time: Operator:
Activit[Mg 2 uCi/ml 6Tu uC1/mi l 2"Na 10lic pCi/ml uCi/ml 187W 122Sb uCi/ml uti/mi ]
56Mn uCi/ml 9%3Tc uti/ml ]
3H uCi/ml I, pH Comments:
I Analysis Performed:
Date: Time: Technician:
MURR PRIMARY WATER ANALYSIS I_ Sample drawn:
Date: Time: Operator:
I Activity:
2'Mg uCi/mi 187W uCi/ml 2"Na pCi/ml 13II uti/ml 93DTc uti/mi 1321 uCi/ml 56Mn uCi/ml 1331 uti/ml 594n uCi/ml 1341 uC1/ml 64Cu pCi/ml 3H uCi/ml ;
pH Comments:
I Analysis Performed:
Date: Time: Technician:
Rev. 5/02/89 App'd 1AM SOP /A-15a ]
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Rev. 5/02/89 App'd ! 9% S0P/A-15b ]
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] ilIl
]
. a 6
1
_ s =_ -
_l a At i
/e t _
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- i O e
-- nI _
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c _
- i v
r e _
_S _
m ._
n o
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a _
c o
_L _
m _
D _
E B _ _
R _ _
O _ _
F _
G _ _
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L _ _
N _
I S
_d B e _
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R _f S _o _
E _s I u _
R t mSE S
t a .
0 _
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m _
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p M i T
=
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5 D
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I I NOTE: THIS PAGE INTENT 10tqALLY LEFT BLANK -
Io %
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I g
I I 4 I ?
I Rev. 5/02/89 App'd (AlpM SOP /A-16b ]
Rset
O MI ,
P T C r c.
o O A O E Y /
R T T I
S w O
e i H R f C E /,
N R A
V t
t i u r E U S_ o_
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a urs w
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'N R T P. _
O U N O U _
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- T T f
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iWt _
O O A MO
- tH _
t S f S .
- R .
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- 6 4 6 R
8 f HT .
f O T O O N
F O
_ O tt t _
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A A _ O _.
P M V . P H 7 t /
5 f O u N D
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T E A
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, 9 E H
T M 9 1 1 o OC t
g
, ' ,^
/
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Rev. 5/02/89 App'd (M SOP /A-17b ]
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1 i
IEntn YeaF= 1 D. I. WATER MAKEUP LOG 1 (Fill in only if sending D.I. water.) ]
l Time Conductivity Water Meter Pre- 4' Day Start i Stop R0 T-300 Start l Stop l Net Filter REMARKS Unit Start Stop aP 1
l l
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Rev. 5/02/89 App'd b SOP /A-18b ] '
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MURR OPERATOR ACTIVE STATUS LOG ]
OPERATOR NAME: ]
YEAR: 3 NOTE: This form is for documenting on-shift activities of ]
licensed operators not normally assigned to rotating shifts. ]
QUARTER 1 ]
Active status needs to be documented Reactor Manager Initial ]
to meet minimun requirements (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) ]
Active status lapsed, documentation required ]
for return to active status (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). ]
I Date Start Time Finish Time Total Time SR0 Initial ]
]
3
]
]
]
QUARTER E ]
Active status needs to be documented Reactor Manager Initial ]
to meet minimun requirements (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) .]
Active status lapsed, documentation required ]
for return to active status (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). ]
Date Start Time Finish Time Total Time SRO Initial ]
-]
]
]
I ._
]
]
NOTE: On-shift activities must be performed in one (1) hour or greater intervals. ]
Orig. 5/02/89 _
App'd Wh SOP /A-19a
MURR OPERATOR ACTIVE STATUS LOG (cont'd) ]
OPERATOR NAME:
YEAR:
NOTE: This form is for documenting on-shift activities of T licensed operators not normally assigned to rotating shifts.
QUARTER 3 -
Active status needs to be documented Reactor Manager Initial ]
to meet minimum requirements (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Active status lapsed, documentation required g for return to active status (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). E Date Start Time Finish Time Total Time SR0 Initial 1
_ E
]
I
]
Active status needs to be documented Reactor Manager Initial ;
to meet minimum requirements (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) l Active status lapsed, documentation required ]
for return to active status (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />).
Date Start Time Finish Time Total Time SR0 Initial I'i l
NOTE: On-shift activities must be performed in one (1) hour or greater intervals.
Ori g . 5/02/89 App'd h% SOP /A-19b Il
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i APPENDIX B ;
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I T0XIC MATERIALS WITH RESTRICTED USE j IN THE CONTAINMENT BUILDING l l
l 1 Any potentially hazardous material or chemical not listed below (flammable, ]
o readily dispensable, aromatic, aerosol), shall be approved by the Shift Supervisor ]
(using the book " Dangerous Properties of Industrial Materials" as reference) before ]
being brought into containment. ]
The following materials in potentially hazardous quantities and readily ]
dispensable forms are NOT permitted in the containment building. ]
NOTE: This is only a partial list, always check with the Shift Supervisor ]
before bringing any new materials or chemicals into containment. ] l Acetone Ammonia I Antimony and compounds Arsenic and compounds Bromine Carbon dioxide I Carbon monoxide Chlorine Chlorine dioxide Chlorine trifluoride Chloroform (trichloromethane)
Chromium, sol. chromic, chromous salts as Cr I Cyanide (as CN)-Skin 2, 4-D DDT-Skin Ethyl alcohol (ethanol)
Ethyl ether Fluorine Formic acide Hafnium Hydrogen bromide Hydrogen chloride I Hydrogen cyanide-Skin Hydrogen peroxide (90%)
Hydrogen selenide I Hydroquinone Iodine Isopropyl alcohol l
J L.P.G. (liquified petroleum gas) j I Manganese Mercury i
1 Mesityl oxide Rev. j/02/89 App'd M SOP /B-la ]
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- T0XIC MATERIALS WITH RESTRICTED USE IN THE CONTAINMENT BUILDING (cont'd)
Methyl alcohol (methanol)
Molybdenum: Soluble compounds-Insoluble compounds Naphtha (coaltar)
Naphthalene Nickel, metal and soluble cmpds, as Ni Nitric acid Nitric oxide Nitroglycerin-Skin Nitromethane Ozone-g Perchloric acid g Phosgene (carbonyl chloride)
Phosphoric acid Phosphorus Propane i Sodium hydroxide St rychnine .
Sulfuric acid Trinitrotoluene-Skin Uranium: Soluble compounds-Insoluble compounds I
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I Rev. 5/02/89 App'd (MM S0P/B-lb ]
Reset I
's; EMERGENCY PROCEDURES (dated January 1985 and revised May 13,1988)
NOTE: New manual printed itay 13,1988)
. REVISION NO. 1 Section No. . Page No. Date P.evised SEP-7 1 1/11/89 SEP-9 .1 1/11/89 I .
HOTE: SEP-7, page 2: Social Security Numbers have been omitted per request by Nuclear Regulatory Commission, Al Adams, 9/87.
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I 11-3 I .
SEP-7 (Cent'd) Page 2 of 4
- 5. The UR staff member contacted should verify a call concerning an emergency at the University of Missouri Research Reactor by calling 882-4211 or 874-4119 and ask to speak to a member of the Facility ,
Emergency Organization (FEO). If the person answering the phone does l not know who is in the FEO, then ask for anyone from the Director's Office, Operations, Health Physics, or Reactor Chemistry groups. The individuals in these groups are listed below in alphabetical order.
Af ter verifying the person's identity by asking for his social security.
number, the emergency call can be verified.
VERIFICATION LIST FOR M3RR EMERGENCIES Name Soc. Sec. No. Name Soc. Sec. No.
Don Alger Mike Kilfoil Chuck Anderson Ron Kitch Brian Barker Sue Langhorst Joe Baskett Charlie McKibben Rita Bonney Walt Meyer Kenneth Beamer Steve Morris Barry Bezenek Leslie Powell ;
Robert Brugger Mike Randolph.
Ron Dobey Bill Reilly ]
Chester Edwards Tony Schoone John Ernst Jim Schuh ]
Christine Errante I Mac Evans Les Foyto ]
Tom Seeger Vickie Spate Ray Stevens John Fruits ] Jim Swallow I Greg Gunn Robert Hudson Nolan Tritschler Mike Wallis Rolly Hultsch Tim Warner Brenda Johnson Vernon Jones
~g 6. UR personnel contacted will determine the need for staffing and equipping E an emergency information center and will call in the required staff and arrange for necessary facilities at 828 Lewis Hall.
l 7. UR personnel will inform news' media and others of the public, as neces-sary, of the emergency.
i
' l 8. If possible, a UR staff, member will be sent on site to assist the EMERGENCY DIRECTOR with the release of information.
e a.
Rev. 1/11/89 App'd I N# 7\.
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Page 1 of 2 g l .SEP-9 i .' TRAINING PROCEDURE FOR ENERGENCY PREPAREDNESS I.- TRAINING OF EMERGENCY ORGANIZATIONS.
A. FACILITY EMERGENCY ORGANIZATION (FE0) TRAINING g This' organization consists.of WRR staff in the Director's Office, g
Operations,- Health Physics and Reactor Chemistry groups. .This: organi-ration will respond to both GENERAL FACILITY EMERGENCIES (FACILITY L EVACUATION,' REACTOR ISOEATION, FIRE. MEDICAL AND SECURITY EMERGENCIES)
.and EMERGENCIES WITH POSSIBLE OFFSITE CONSEQUENCES (UNUSUAL EVENT, ALERT.-
SITE AREA EMERGENCY, PARTIAL SITE AREA EVACUATION). I I
- 1. The members of the FE0 will train initially and annually thereafter, by emergency plan and procedure review of each member's role in
~'
emergency preparedness. This training will be documented by each member signing the EMERGENCY PLAN / PROCEDURES REVIEW DOCUMENTATION LIST.
- 2. Annual onsite emergency drills shall be conducted as action drills I to' test the training of FE0 members ?.o carry out their roles under.
simulated emergency conditions.
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B. TRAINING.OF FACILITY STAFF OTHER THAN FE0' MEMBERS -
-1. The members of WRR staff not assigned to the FE0 shall initially and annually thereafter be trained as to their respective actions for each site and facility emergency classification. This training may be by seminar, lecture, or video tape sessions.
- 2. Annual onsite emergency drills will test these members' ability to properly respond to simulated emergency conditions.
^
C. TRAINING OF EMERGENCY SUPPORT ORGANIZATIONS
- 1. The members of EMERGENCY SUPPORT ORGANIZATIONS shall be trained initially and biennially thereafter on their role in maintaining Emergency Preparedness. This will be performed by discussions between W RR staff and the members of each SUPPORT ORGANIZATION,
)
stressing familiarization with the facility or changes to the '
emergency plan or procedures. This training will be scheduled 1
~
prior to each biennial drill and will include drill planning and 3 i scenario development. ] j
- 2. Biennial emergency drills shall be conducted to test, .as a '
minimum,' the communication link and notification procedures with these EPERGENCY SUPPORT ORGANIZATIONS.
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a ,f.
sRev. 1/11/89 App'd, M ,. ,Vr%
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. 7 _ e
- I EMERGENCY PROCEDURES (dated January 1985 and revised May 13,1988) i-NOTE: New manual printed May -13,1988)
REVISION NO. 2 l Section No. Page No.
1 Date Revised 5/22/89 EMERGENCY CALL LIST I .
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t SECTION III I REVISIONS TO THE HAZV DS
SUMMARY
REPORT 1 July 1988 tnrough 30 June 1989 HAZARDS
SUMMARY
REPORT (original July 1,1965)
I Section 8.4 of Original Hazards Summary:
This section was revised in its entirety in the 1987-1988 Annual Report. The last sentence of the third paragraph of that revision should be changed from: g "The graphite elements at positions 5A, 5B and 6 have been replaced with elements that each accommodate a 5-1/2 inch 0.D. irradiation basket."
to:
"The graphite elements at positions SA and 5B have been replaced with elements that each accommodate a 5-1/2 inch 0.D. irradiation basket. The graphite element at position 6 has been replaced with an element containing a solid graphite block which provides one 3 inch 0.D. irradiation I basket and a 1/4 inch I.D. hole to house self-powered neutron detectors."
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I 111-1
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SECTION IV l
PLANT AND SYSTE!! 110 DEIFICATIONS 1 July 1988 through 30 June 1989 SEPTEf1BER 1988 liodification 88-3: This modification replaces a refle'ctor Gement installed in February 1988 (reported as flodification 87-1 in the 198/-88 Annual Report). The element replaced had a 5-1/2" diameter irradiation position and contained neutron absorbing material. The new element is con-structed of aluminum and graphite and has a 3" diameter irradiation basket.
The new element, like the element it replaces, has been designed to allow reflector element removal withcut withdrawing the beam tube. This was accomplished by omitting the lower hook section that encircled Beamport "D" in the original element design. The safety evaluation for this modification documents that it does not present an unrtviewed safety question as per 10 CFR 50.59.
OCTOBER 1988 flodification 88-8: This mod'ification record documents the sealing of the containment building internal surfaces with an elastomeric resin-water base copolymer coinpound (commercial name, Decadex). The surfaces sealed were the north, west and south containment walls, the walls of the pipe chase on the south wall of containment, the underside of the prestressed beams in the containment ceilitig, and the walls and ceiling of the north laboratory area on the beamport floor.
Addendum 2 of 11URR Hazards Summary Report discusses the application of a sealant to the concrete containment walls to enhance leak proofing. The sealant used in this modification again only serves to enhance the leak proofing of the containment dalls.
The safety evaluation for this modification documents that it does not present an unreviewed safety question as per 10 CFR 50.59.
IV-1
liAY 1989 11 modification 89-2: This modification bypasses the " blade full-in" photocell when the rod drop timer switch is turned on during the performance of CP-10, the compliance check that measures control blade drop times.
The rod drop timer photocell is located at the 20% withdrawn position and the " blade full-in" photocell is located at the full inserted control blade position. The bypass ensures that the control blade drop time is measured between the control blade full out position and the 20% withdrawn i position as per Technical Specification 3.2.c.
This modification does not effect the rod control system. The rod drop timer circuitry is independent of the rod control system. The safety evaluation for this modification documents that it does not present an unreviewed safety question as per 10 CFR 50.59.
I JUNE 1989 11 modification 89-1: This modification adds an interlock to the pool cleanup pump (P513B) control circuitry to prevent its operation if the pool isolation valve (V509) is not open. Before this interlock was added, it was possible to pump water from the 6,000 gallon holdup tank and an isolated pool system to the bulk pool via the cleanup system if the P5138 pump was inad-vertently left on after closing V509.
This modification provides an interlock to back up the standard oper-ating procedure for securing the pool system. The safety evaluation for this modification documents that it does not present an unreviewed safety question as per 10 CFR 50.59.
I IV-2 l
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SECTION V
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NEW TESTS AND EXPERIMENTS 1 July 1988 through 30 June 1989 I New experimental programs during this period are as follows:
RUR 260 Experimenter: W. Miller
Description:
An addendum was added to the RUR for Bemport "F" to allow experimental determination of the amount of hydrogen in steel.
I RUR 266 Experimenter: S. Gunn
Description:
This RUR authorizes the irradiation of small amounts of dry sodium nitrate to produce a radioactive tracer used by power plants in steam generator carryover tests.
RUR 267 Experimenter: S. Gunn
Description:
This RUR authorizes the production of Ca-45 to be used for tracer experiments in biochemistry.
RUR 268 Experimenter: S. Gunn
Description:
Tnis RUR authorizes the production of Sm-153 for use in medical radiotherapy.
RUR 271 Experimenter: G. Ehrhardt
Description:
This RUR authorizes the production of Y-90 for use in clinical trials to treat liver cancer.
I RUR 272 Experimenter: G. Ehrhardt
Description:
This RUR authorizes the production of Re-186 for 1
nuclear medicine.
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I I' RUR 273 Experimenter: .G. Ehrhardt
Description:
This RUR authorizes the production of W-138/Re-188 generators for nuclear medicine. j RUR 276 Experimenter: S. Gunn
Description:
This RUR authorizes the production of iridium-192 pellets to be used for cedical purposes.
I 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.
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I V-2
SECTION VI SPECIAL NUCLEAR MATERIAL ACTIVITIES 1 July 1988 through 30 June 1989
- 1. SNM Receipts: 7 total of 20 new fuel elements were received from Babcock and W'icox (B & W), Lynchburg, Virginia.
Grams Grams Shipper _ Elements' U U-235 B&W M0272 M0273, M0274, M0275, M0276, 16,595 15,459 M02Ti, M0278, M0279, M0280, M0281, M0282, M0283, M0284, M0285, M0286, M0287, M0288, M0289, M0290, M0291
- 2. SNM Shipments: A total of 32 spent fuel elements were shipped to Westinghouse Idaho Nuclear Co., Irc. Idaho Falls, Idaho, for reprocessing.
Grams Grams Shipp,er Elements _
U U-235 MURR M0143, M0205, M0211, M0213, M0215, M0216, 21,872 19,182 M0217, M0218, M0220, M0222, M0223, M0224, M0225, M0226, M0227, M0228, M0229, M0230, M0231, M0233, M0235, M0236, M0237, M0238, M0242, M0243, M0244, M0245, M0250, M0251, M0252, M0253
- 3. Inspections: Physical security and SNM accountability inspections were conducted by the Nuclear Regulatory Commission (NRC), during the time period October 25-27, 1988. The MURR Special Nuclear Material Control Procedures were reviewed in July 1988 by the Procedures Review Subcommittee (of the Reactor Advisory Committee) as per the annual requirement.
l 4. SNM Inventory: As of 30 June 1989, MURR was financially responsible for the following DOE owned amounts:
Total U = 33,298 grams Total U-235 = 29,764 grams Included in these totals are 36 grams of U and 34 graas of U-235 non-fuel, DOE owned, in addition to t,hese totals, MURR owns 15E grams of U and 74 grams of U-235. All of this material is physically located at the MURR.
VI-1
Fuel elements on hand have accumulated. the following burnups as of 30 June 1989:
Element No. MWD Element No. MWD Element No. MWD p
MO-232 145.46 M0-262 129.63 M0-277 77.33 M0-234 145.46 M0-263 135.36 MO-278 76.04 MO-239 145.05 M0-264 129.63 M0-279 77.33 M0-240 145.05 M0-265 135.36 M0-280 72.70 M0-246 143.80 M0-266 132.01 M0-281 52.60 M0-247 146.78 M0-267 123.08 M0-282 72.70 MO-248 143.80 M0-268 132.01 MO-283 52.60 M0-249 146.78 M0-269 123.08 MO-284 38.91 M0-254 146.15 M0-270 120.25 M0-285 34.19 M0-255 126.70 M0-271 120.25 M0-286 38.91 M0-256 146.15 M0-272 83.89 MO-287 34.19 M0-257 126.70 MO-273 79.59 M0-288 13.28 M0-258 134.19~ M0-274 83.89 M0-289 6.27 M0-259 135.40 M0-275 79.59 M0-290 13.28 M0-260 134.1.9 M0-276 76.04 MO-291 6.27 M0-261 135.40 _,,,,
TOTAL 4,597.32 Average Burnup 99.94 MWD VI-2
a SECTION VII REACTOR PHYSICS ACTIVITIES 1 July 1988 through 30 June 1989
- 1. . Fuel utilization: During this period, the following ele:nents reached licensed or feasible burnup and were retired.
Serial Number Final Core Date Last Used 11WDs (10205 88-31 7-07-88 135.71 M0217 88-31 7-07-88 135.71 110232 89-12 3-20-89 145.46 M0234 89-12 3-20-89 145.46 110235 88-37 8-10-88 124.60 I10236 88-36 8-04-88 127.54 110237 88-37 8-10-88 124.60 M0238 88-36 8-04-?8 127.54 110239 89-11 3-13-89 145.05 110240 89-11 3-13-89 145.05 110242 88-52 10-27-88 131.06 110243 88-51 10-20-88 113.90 110244 88-52 10-27-88 131.06 110245 88-51 10-20-88 118.90 t10246 89-20 4-29-89 143.80 f I
110247 89-24 5-22-89 146.78 110248 89-20 4-29-89 143.80 i10249 89-24 5-22-89 146.78
!!0250 88-52 10-27-88 132.29 110251 88-51 10-20-88 113.98 H0252 88-52 10-27-88 132.29 110253 88-51 10-20-88 118.98 V11-1 I
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Serial Number F_inal Core Date Last Used 11WDs 110254 89-25 5-30-89 146.15 i M0255 89-18 4-18-89 126.70 110256 89-25 5-30-89 146.15 110257 89-18 4-18-89 126.70 t10259 89-22 5-08-89 135.40 M0261 89-22 5-08-89 135.40 110263 89-23 5-15-89 135.36 M0265 89-23 5-15-89 135.36 Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial criticalities are obtained with four new elements or fewer as conditions dictate. A core desi9 nation consists of eight fuel elements of which only the initial critical fuel Element serial ndabers are listed in the following table. To increase operating efficiency, fuel ele-ments are used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number.
Fabrication Serial Initial Core Initial Core No. No. Load Number Operating Date 49 110266 88-30 6-23-88 49 M0267 88-31 6-30-88 49 110268 88-30 6-23-88 49 110269 88-31 6-30-88 The above four elements should have Deen included in 87-88 Annual Report.
49 110270 88-36 7-28-88 49 (10271 88-36 7-28-88 50 110272 88-48 9-22-88 50 M0273 88-49 9-29-88 50 :10274 88-48 9-22-88 VII-2 E l
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Fabrication Seri al Initial Core Initial
- I' Core No. No. hadNumber Operating Date
- 50 110275 88-49 9-29-88 f
88-58 11-17-88 50 M0276 50 M0277 88-60 11-23-88 2 50 M0278 88-58 11-17-88 50 M0279 88-60 11-23-88 51 M0280 89-4 1-26-89 51 M0281 89-6 2-09-89 51 M0282 89-4 1-26-89 51 M0283 89-6 2-09-89 51 M0284 89-20 4-24-89 51 M0285 89-22 5-01-89 51 M0286 89-20 4-24-89 51 M0287 89-22 5-01-89 52 M0288 89-89 6-13-89 52 M0289 89-33 6-26-89 52 M0290 89-29 6-13-89 52 M0291 89-33 6-26-89
- 2. Fuel Shipping: Thirty-two spent fuel elements were shipped from 11URR to Westinghouse Idaho Nuclear Co., Inc. Idaho Falls, Idaho. The identification numbers of these elements are:
M0143 M0217 M0225 M0231 M0242 M0252 4
h M0211 M0220 M0227 M0235 M0244 M0213 M0222 M0228 M0236 M0245 M0215 M0223 M0229 M0237 M0250 4
I. M0216 M0224 M0230 M0238 M0251 l V11-3 l
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- 3. Fuel Procurement: Babcock and Wilcox, Lynchburg, Virginia is MURR's current fuel assembly fabricator. This work is contracted with the U. S. Department i of Energy and administered by E G & G Idaho, Idaho Falls, Idaho. As of 1
30 June 1989, ninety-one fuel assemblies fabricated by Babcock & Wilcox had been received and ninety-one used in cores at 10 MW.
l 4. Licensing Activities: On October 20, 1988, the Nuclear Regulatory l Commission approved Amendment No.16 to the Facility Operating License No.
I R-103.
The amendment (1) authorizes an increase in the amount of depleted urantum that may be received, possessed, and used f rom 20 kg. to 50 kg., (2) authorizes the receipt, possession, and use of up to 40 grams of plutonium in the form of a sealed rod source, (3)
I removes the requirement that the pool cooling system pumps operate in parallel, (4) updates the facility organizational structure, and (5) corrects a typographical error and replaces references to the AEC with NRC.
On February 16, 1989, the Nuclear Regulatory Commission approved Amendment No.17 to the Facility Operating License No. R-103.
This amendment restored the phrase "to which the system was originally designed and fabricated or to specifications" that had been renoved from Technical Specification 6.1.e in error in a previous Technical Specification Amendment request (Anendment No. 16).
On May 8,1989, the Nuclear Regulatory Commission approved Amendment No.
18 to the Facility Operating License No. R-103.
This amendment, effective Ju?y 1,1989, approved the new administrative organization chart that reflects the shift of administrative authority for the MURR from the University of Missouri System to the University of Missouri at Columbia.
I VII-4
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- 5. Reactor Characteristic Measurements: Seventy-one refueling evolutions were completed. An excess reactivity verification was performed for each refueling and the average excess reactivity was 1.7%. MJRR Technical Specification 3.1(f) requires that the excess reactivity be less than 9.8%.
Reactivity measurements were performed for 18 evolutions to verify reactivity parameters for the flux trap. Five shim and regulating blade
. calibrations were performed. Three measurements were made of the worth of irradiation wedge replacement.
Physical inspections of the following fuel elements were performed to verify the operational parameters.
M0248 from Core 47 2/3/89 M0240 from Core 46 2/6/89 M0232 from Core 45 2/6/89 M0256 from Core 48 5/5/89 All measurements were within operational requirements.
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I N
k VII-5 I
I SECTION VIII
SUMMARY
OF RADIOACTIVE EFFLUENT RELEASED TO THE ENVIRONMENT Sanitary Sewer Effluent 1 July 1988 through 30 June 1989 Descending Order of Activity Released for Totals > 1.00E-5Ci i
Nuclide Amount (C1) Nucli d_e. Amount (Ci) Nuclide Amount (Ci) 3.52E-02 Re-186 3.00E-04 Se-75 4.31E-05 H-3 I S-35 As-77 4.00E-03 1.44E-03 Sm-153 Na-24 2.32E-04 1.23E-04 Rb-86 Sc-46 4.15E-05 4.03E-05 7.04E-04 Cd-109 9.53E-05 Eu-152 3.45E-05 i Zn-65 4.76E-04 Cu-64 5.92E-05 Cr-51 2.08E-05 P-32 4.74E-04 Ag-110m 5.74E-05 Gd-159 1.77E-05 Co-60 Te-125m 3.86E-04 I NOTE: Du ing FY88 and FY89, a decrease in tritium concentration released from the ifJRR gaseous effluent Was investigated. On July 29, 1988, the cause I was found to be the result of improvements made on the facility air con-ditioning system. Airborne tritium removed by the air conditioner was discovered in the consensate line, which was being released to the storm sewer system. The condensate line was rerouted on August 23, 1988 to empty into the waste tank system to ensare mnitoring of the tritium prior to release. Release concentrations to unrestricted areas were esti-mated to be less than 4.10 E-04 uCi/ml (147, MPC, Table II) during the period of identified release to the storm sewer: April 28,1988 through August 23, 1988. Total release was estimated to be 0.1 Ci f ron April 28, 1988 to June 30,1988 and 0.07 Ci fren July 1,1988 to August 23, 1988.
The total tritium release through the air conditioning line from August 24, 1988 to June 30, 1989 is included in the 0.035 Ci reported for j tritium in this. sanitary sewer releas'e report. Comparing these results, the release of tritium to the storm sewer system is believed to be con-I servative in its'over-estimation.
I I Vill-1 E
Stack Effluent 1 July 1988 through 30 June 1989 Ordered by % of Technical Specification (TS) Limit Isotope Total Release Est. Ave. TS Limit Percent TS*
I FY89 (Ci) __
Conc.
( tC1/mQ, _
(X MPC)
Ar-41 9.2E+02 3.6E-06 350 25.857 I 1-131 1.2E-03 9.7E-12 1 9.667 K-40 5.3E-04 4.2E-12 1 4.215 Eu-154 l'.9E-05 1.5E-13 1 0.147 i 1-135 2.0E-02 1.6E-10 350 0.046 I-133 3.0E-03 6.3E-11 350 0.045 Eu-152 1.9E-05 1.5E-13 1 0.037 l
Co-60 9.0E-06 7.1E-14 1 0.024 _
1-134 5.7E-02 4.5E-10 350 0.022 Se-75 9.1E-05 7.2E-13 1 0.018 H-3 2.8E+00 1.1E-08 350 0.016
.I -
Cd-109 3.9E-05 3.0E-13 1 0.015
~
Ce-144 3.7E-06 2.9E-14 1 0.014 I-132 1.5E-02 1.2E-10 350 0.011 Ce-139 1.3E-06 1.0E-14 1 0.010
~
Hg-203 5.1E-05 4.0E-13 1 0.010 I V-52 1.3E-01 1.0E-09 350 0.010 _
Na-22 2.7E-06 2.1E-14 1 0.007
~
Cs-137 2.6E-06 2.1E-14 1 0.004 Xe-135m 4.7E-02 3.7E-10 350 0.004 l
l VIII-2
p I
I Isotope Total Release Est. Ave. TS Limit Percent TSO FY89 Conc. (X MPC) u (Ci) { tCi/ml) _ _ ,
Br-82 9.2E-03 7.3E-11 350 0.003 Te-125m 1.2E-05 9.5E-14 1 0.002 C1-38 5.8E-02 4.6E-10 350 0.002 Eu-155 5.6E-06 4.5E-14 1 0.001 Zr-95 1.7E-06 1.3E-14 1 0.001 Zn-65 3.3E-06 2.6E-14 1 0.001 Te-123m 1.6E-07 1.3E-15 1 0.001 1-128 1.6E-02 1.3E-10 350 0.001 Pd-109 4.6E-03 3.7E-11 350 0.001 Ba-140 1.2E-06 9.5E-15 1 0.001 Ng-27 1.2E-02 9.8E-11 350 0.001 Ag-110m 3.3E-07 2.6E-15 1 0.6 31 As-77 2.8E-03 2.2E-11 350 0.001 Mn-54 7.3E-07 5,8E-15 1 0.001 Co-57 4.0E-06 3.2E-14 1 0.001
- 1sotopes observed at <0.001% TS limit not listed.
Stack flow rate - 17,100 cfm.
I .
I E VIII-3 I
I SECTION IX Sutt!1ARY OF ENVIRONitENTAL SURVEYS 1 July 1988 through 30 June 1989 t
Environmental samples are collected two times per year at eight locations and analyzed for radioactivity. These locations are shown in Figure 1. .%il 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 October 1988.
Detection Limits
- lfatrix Alpha Beta Gamma Tritium Water 0.8 pCi/1 2.2 pCi/1 225.0 pCi/1 18.1 pCi/ml of sample Soil 0.8 pCi/g 2.3 pCi/g 1.6 pCi/g N/A Vegetation 1.6 pCi/g 4.7 pCi/g 2.7 pCi/g 18.1 pCi/g of distillate I
- Gamma and tritium analyses are based on wet weights while alpha and beta analysis are based on dry weights.
Determined Radioactivity Levels Vegetation Samples I Sample Alpha (pCi/Q Beta (pCi/g)
Gamma Mi/g)
Tritium (pCi/g) 1-V-34 < 1.6 12.7 < 2.7 < 18.1 2-V-34 < 1.6 6.5 < 2.7 < 18.1 3-V-34 < 1.6 9.5 < 2.7 < 18.1 4-V-34 < 1.6 13.7 < 2.7 < 18.1 5-V-34 < 1.6 9.? < 2.7 < 18.1 6-V-34 < 1.6 5.8 < 2.7 < 18.1 7-V-34 < 1.6 6.7 < 2.7 < 18.1 10-V-34 < 1.6 13.1 < 2.7 < 18.1 I
l l IX-1 I
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Determined Radioactivity Levels Soil Samples Sample Alpha Beta Gamma (pCi/g) (pCi/g) (pCi/g)
[
1-S-34 1.2 12.1 6.7 2-S-34 < 0.8 10.7 5.9 3-S-34 1.2 11.6 5.3 4-S-34 < 0.8 10.1 5.2 5-S-34 < 0.8 9.0 6.8 6-S-34 < 0.8 4.1 5.3 7-S-34 < 0.8 7.9 6.8 10-S-34 < 0.8 5.8 6.0 Determined Radioactivity Levels Water Samples Sample Alpha Beta Gamma Tritium (pCi/1) (pCi/1) (pCi/11 (pCi/mi) 4-W-33 < 0.8 15.9 < 225.0 < 18.1 6-W-33 < 0.8 5.5 < 225.0 < 18.1 10-W-33 < 0.8 2.0 < 225.0 < 18.1
- 2. Sampled during April 1988. !
]
Detection Limits
- Matrix Alpha Beta Gamma Tritium Water 0.9 pCi/l 2.6 pCi/l 219.0 pCi/l 16.2 pCi/ml j of sample l Soil 1.0 pCi/g 2.7 pCi/g 1.2 pCi/g N/A j Vegetation 2.2 pCi/g 6.2 pCi/g 2.9 pCi/g 16.2 pCi/g of distillate
- Gamma and tritium analyses are based on wet weights while alpha and beta analysis are based on dry weights.
IX-3
)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i
l 1
!. Determined Radioactivity Levels !
Vegetation Samples l
- . Sample Alpha Beta Gamma Tritium (pCi/g) (pCi/g) (pCi/g) (pCi/g) 1-V-35 < 2.2 20.9 < 2.9 < 16.2 -
j I. 2-V-35 < 2.2 17.0 < 2.9 < 16.2 'i l
3-V-35 < 2.2 26.3 < 2.9 < 16.2 l
.I. 4-V-35 < 2.2 19.5 < 2.9 < 16.2 i i
5-V-35 < 2.2 19.3 < 2.9 < 16.2 6-V-35 < 2.2 21.4 < 2.9- < 16.2 7-V-35 < 2.2 32.1 < 2.9 < 16.2 10-V-35 < 2.2 21.3 < 2.9 < 16.2 Determined Radioactivity Levels Soil Samples Sample Alpha Beta Gamma (pCi/g) (pCi/g) (pCi/g) 1-S-35 < 1.0 9.2 6.3 2-5-35 < 1.0 9.7 5.9 3-S-35 < 1.0 12.2 5.5 4-S-35 < 1.0 6.9 3.0 5-S-35 < 1.0 11.9 5.3 6-S-35 < 1.0 9.3 4.9 5.7 7-S-35 < 1.0 9.7 10-S-35 < 1.0 8.0 7.0 I
IX-4 I
Determined Radioactivity Levels Water Samples Sample Alpha Beta Gamma Tritium (pCi/1) (pCi/1) (pCi/1) (pCi/mi)
I-4-W-35 < 0.9 < 2.6 < 219.0 < 16.2 6-W-35 < 0.9 4.1 < 219.0 < 16.2 10-W-35 < 0.9 6.9 < 219.0 < 16.2 I
Environmental samples were also collected around Sinclair RAD WASTE Facility at four locations. Soil and vegetation samples were taken at each location.
Results of these samples, are shown in the following tables.
- 1. Sampled during October 1988.
Detection Limits
- itatri x Al pha Beta _ Gamma Tritium Soil 0.8 pCi/g 2.3 pCi/g 1.6 pCi/g N/A Vegetation 1.7 pCi/g 4.9 pCi/g 3.6 pCi/g 18.1 pCi/g
- Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
Determined Radioactivity Levels Veg_etation Samples Sample Alpha Beta Gamma Tritium (pCi/g) (pCi/g) (pCi/g) (pCi/g)
SF-1-V7 < 1.7 22.3 < 4.9 < 18.1 SF-2-V7 2.5 21.0 < 4.9 < 18.1 SF-3-V7 < 1.7 19.1 < 4.9 < 18.1 SF-4-V7 < 1.7 17.9 < 4.9 < 18.1 I
IX-5 I
I .
I Determined Radioactivity Levels Soil 5amples
. Sample Alpha Beta Gaiama (pCi/g) (pCi/g) (pCi/g)
,SF-1-57 1.0 10.7 7.6 SF-2-S7 < 0.8 11.6 6.1
.SF-3-57 < 0.8 12.2 8.2 SF-4-S7 !.6 14.6 7.3 I 2. Sampled during Ap ?1 1989.
Detection Limits
- llatri x Alpha Beta Gamma Tritium Soil 1.9 pCi/g 5.3 pCi/g 1.4 pCi/g N/A Vegetation 1.8 pCi/g 5.2 pCi/g 3.4 pCi/g 16.2 pCi/g
- Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
I E oetermined Radioactivity Levels E Vegetation Samples Sample Alpha Beta Gamma Tritium I (pCi/Q
< 1.8 (pCi/g 18.8 (pCi/g)
< 3.4 (pCi/g)
< 16.2 SF-1-V9 SF-2-V9 < 1.8 16.2 < 3.4 < 16.2 SF-3-V9 < 1.8 17.0 < 3.4 < 16.2 SF-4-V9 < 1.8 20.0 < 3.4 < 16.2 I
IX-6
. I:
I Determined Radioactivity Levels Soil Samples Sample Alpha Beta Gamma I (pCi/g) 1.9 (pCi/g) 16.4 (pCi/g) 5.9 SF1-59 l-E SF2-S9 < 1.9 < 5.3 1.4 SF3-.S9 < 1.9 8.5 8.0 SF4-59 < 1.9 7.8 6.5 I RADIATION AND CONTAi11NAT10N SURVEYS The following table gives the number of surveys performed during FY 89.
Radiation Surface Contamination Air Samples 1988 July 40 38 21 I August 49 45 23 September 28 24 22 October 37 36 21 November 41 38 21 December 45 46 22 I 1989 January 33 32 21 February 54 42 20 41 35 23 I
11 arch April 38 37 20 1 lay 47 52 22 June 32 36 22 77 Radiation Work Permits were issued during the year.
l l-IX-7 1
I 4 I j o
Miscellaneous Items The new Health Physics Technician position was filled by Joseph DeMers in January 1989. Mr. DeMers was honorably discharged from the Navy in December 1988, where he had gained experience as .a Leading Engineering Laboratory Tech-nician and a trainer at the Naval Nuclear Power Training Unit in New York. As of September '1988, John Ernst (Health Physicist) became a Certified Health Physicist (CHP) after successfully completing the examination given by the American Soard of Health Physics (ABHP). Dr. Susan Langhorst (Manager, Reactor Health Physics and CHP) was appointed to a three year term on the Panel of Examiners for Part Two of the ABHP Certification Examination.
Health Physics Procedure #33, " Operation of Sample Counting Systems" was added to the HP SOPS and Health Physics Procedure #27, " Calibration of Sample Counting Systems" was modified in order to incorporate the instructions for using the Canberra Model 2400 Alpha / Beta / Gamma System. Copies of these pro-cedures are attached at the end of this section.
ADC0 Services, Inc. has continued to act as our institutional waste broker. Through ADCO, MURR disposed of 487.5 cubic feet of LSA material gen-erated at MURR. In addition, a dedicated waste shipment was made through Chem I Nuclear to dispose of 13.1 cubic feet of irradiated metal hardware consisting of used graphite elements and miscellaneous activated reactor components.
As anticipated, the production of radioisotopes used in radiopharmaceuti-cals at MURR has continued to grow. Phase Two clinical trials utilizing the l
Sm-153 bone agent produced at MURR is expected to require the handling of two to four times the activity currently being handled. Extremity doses expected from handling these amount of Sm-153 with the current equipment and procedures were j
considered to be unacceptable for ALARA. Therefore, a dedicated facility was designed and built to remotely perform the manipulations required to handle the IX-8
I increased Sm-153 activity and to also ensure the sterility of producing the final drug product. The extremity monitoring used during the handling of these radioisotopes, as described in the MURR Operations Annual Report 1987/88, has shown that gamma radiation makes up the majority of the extremity exposures.
The data for the cases where beta radiation exposure has been detected on the extremity badges have been reviewed by Dr. Craig Yoder of Landauer. Correction f actors have been estimated by Dr. Yoder to adjust the readings recorded by the ring badge data to account for the component of beta dose recorded by the wrist badges. This collaboration between Drs. Langhorst and Yoder is continuing.
I I
I I
I i
i l
IX-9 1
j
CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES MADE FROM 1 JULY 1988 THROUGH 30 JUNE 1989 There were two revisions (#HP-27 and #HP-33) to the Health Phyysics 50P l manual during the year. These revisions are contained in this section.
1 l
IX-10
I SOP HP-27 Rev. 3 Page 1 of 11 Appr'd ,6 M Date /2 /)l8 e Calibration of Sample Counting Systems I. Policy Sample data that has a direct ef fect on radiation risk evaluation shall be counted with a calibrated instrument.
II. Purpose The purpose of this procedure is to establish a standard method for the calibration of the following counting systems:
A. Canberra Model 2400 Alpha / Beta / Gamma System.
B. Baird Polyspec Research Spectrometer.
C. Eberline Model BC-4 Beta Counter.
III. Procedure--Canberra 2400
- h. Determining the operating voltage. ;
- 1. Use Pu-239 calibration source for alpha counting only.
- 2. Use SrY-90 calibration source for beta and simulta-neous alpha / beta counting.
- 3. Place proper calibration source in planchet and load into elevator magazine.
- 4. Press [ ADVANCE] [ ADVANCE).
- 5. Press [ PLATEAU].
I 6. Choose a time increment that will yield approximate-ly 10,000 counts in the plateau.
- 7. Set discriminator window to 0, press [ ENTER].
- 8. With printer on line, a graph of the plateau curve will automatically print. Choose an operating voltage 50 volts above the knee of the curve.
NOTE: For simultaneous alpha / beta counting, III.B and III.C must be completed. For alpha or I beta only, go to step III.D.
I -- --- ~ ~ - - - -
SOP HP-27 Rev. 3 Page 2 of 11 Appr'd ,$. )d , Mg Date ll1 /l28 B. Determining window setting:
- 1. Place beta calibration source in planchet and load into elevator magazine.
- 2. Press [ ADVANCE] [ ADVANCE].
- 3. Press [ WINDOW] .
- 4. Select operating voltage determined in III.A.B.
above, press [ ENTER].
- 5. A graph of DISC vs COUNTS will automatically print.
Choose the DISC setting where counts go to zero.
- 6. Optimum window setting is where 0.5-1.0% of beta counts are detected in the alpha channel. To. check the window setting, use the following steps:
- a. Place beta calibration source in planchet and load into elevator magazine.
- b. Press [ ADVANCE] [ ADVANCE).
I c. Edit program 0 in the following manner:
selecting parameter press [ ENTER], if parameter is correct as shown just press [ ENTER] ) .
(after Press [ EDIT] [0] [ ENTER]
PRESET COUNT: [999999]
I -
PSET TIME: [1.00]
HIGH VOLTAGE: Select voltage determined in III. A.8 DISC WINDOW: Select setting determined in III.B.5 I CHI-SQUARE (0=N,1=Y):
ERROR (SIGMA):
REPEAT #: [0]
[1.96]
[0]
A EFFIC (%): [0]
A CROSTLK (%): [0]
A BKGND (C PM ) : [0]
B EFFIC (%): [0]
B BKGND (CPM): [0]
BKGD TIME (M): [0]
VOL UNITS: [0]
3 VOL (EA): [1.00]
ACTIVITY UNITS: [1]
- 3 ALARM (dpm/V)
- [200.0]
I -
I SOP HP-27 Rev. 3 Page 3 of 11 Appr'd 6 ,M /m Date /d2///R
- d. When editing is complete press [RUN] [0]
[ ENTER] [ COUNT] .
- e. Gross alpha and beta counts will print. Divide gross alpha counts into gross beta counts. If the result is 0.5-1.0% the DISC WINDOW is Correct.
- f. If it is not, go back to III .B . 6. c, add 50 to the current DISC WINDOW setting, and repeat I steps d. and e. If the result still does not meet the recommendations, repeat steps c., d.,
and e., adding 50 to the DISC WINDOW each time I until 0.5-1.0% of the beta counts fall into the alpha channel.
C. Measure alpha crosstalk:
- 1. Place alpha calibration source in planchet and load into elevator magazine.
- 2. Press [ ADVANCE] [ ADVANCE].
3.
I Edit program 0 using method described in III.B.6.c.
Enter values for high voltage and disc window deter-mined in steps III.A. and III.B. above.
- 4. Press [RUN] [0] [ ENTER] [ COUNT].
- 5. Gross alpha and beta counts will print. Alpha cross-talk is calculated using the following equation:
Crosstalk = beta counts /(alpha counts + beta counts)
D. Chi-square test:
- 1. Use a combination alpha / beta calibration source or I repeat these steps with an alpha and/or a beta calibration source as needed.
- 2. Place calibration source in planchet and load into elevator magazine.
- 3. Press [ ADVANCE] [ ADVANCE].
I - -
I I SOP HP-27 Rev. 3 Page 4 of 11 Appr'd 6. M.
Date /7///8
- 4. Edit program 0 inserting the values determined in steps III.A-III.C, including the following addi-tional changes to the parameters set in III.B.6.c:
CHI-SQUARE (0=N,l=Y): [l]
REPEAT #: [20]
- 5. Press [RUN] [0] [ ENTER] [ COUNT] .
- 6. The system will count the source 21 times. After the last count, the chi-square value will print.
For 20 degrees of freedom, a chi-square value between 11 and 27 is satisfactory.
- 7. If the chi-square value is not satisf actory, repeat section III.A. If the operating voltage has changed, repeat all parts of section III using the I new high voltage value. If the operating voltage is the same as determined before, repeat the stepG in III.D. Should the results still be unsatisf actory, contact the Health Physics group, and do not use the I instrument for sample counting.
E. Determining efficiencies:
- 1. Place alpha and beta calibration sources in separate planchets. Load the sources, one empty planchet to determine background, and the aluminum end disc into I the elevator magazine.
- 2. Edit a program (normally program 5) in the following I manner: (af ter selecting parameter press [ ENTER] ,
if parameter is -correct as shown just press [ ENTER] ) .
Press [ EDIT] [ program #] [ ENTER]
PRESET COUNT: [999999]
PSET TIME: Select desired count time in minutes, I HIGH VOLTAGE:
(normally 5 minutes)
Select voltage determined in III. A.8 DISC WINDOd: Select disc windod determined in III.B.
START SAMPLE: [0]
l' STOP SAMPLE: [99]
l ERROR (SIGMA): [1.96]
l REPEAT #: [0]
I . . - - _ _ . . _ _ _ . . _ . ._ . .. .. ._ , .. _ _ . . _ . _ _ _ . . . _
i i
j
. . _ _ _ _ _ _ _ __J
SOP HP-27 Rev. 3 Page 5 of 11 Appr'd 8.N, M Date / //% G A EFFIC (%): [0]
A CROSTLK (%): Select value determined in III.C.
A BKGND (C PM ) : [0]
'I B EFFIC (%):
B BKGND (C PM ) :
BKGD TIME (d): [0]
[0]
[0]
VOL UNITS: [0]
~I VOL (EA): [1]
ACTIVITY UNITS: [1]
ALARM (dpm/V): [200]
- 3. When editing is complete press [RUN] [ program #]
[ ENTER] [ RESTACK).
- 4. Ef ficiencies are calculated f rom the following equation:
Ef ficiency = (Gross counts-bkgd)/4 Pi Source dpm
- 5. If efficiency differs from the previous value by I g rea ter than 10 % , contact the Health rhysics group.
Previous values can be found in the instrument log book.
F. Editing counting program:
- 1. Choose counting program to be edited. Program 1 is ,
reserved for normal swipe counting, programs 2-5 are i available for other sample counting procedures.
Enter-parameters in the following manner: (after selecting parameter press [ ENTER], if parameter is correct as shown just press [ ENTER])
Press [ EDIT] [ program #] [ ENTER]
t
~ PRESET COUNT: [999999]
PSET TIME: Select desired count time in minutes HIGH VOLTAGE: Select voltage determined in III.A.8 DISC WINDOW: Select disc window determined in III.B y START SAMPLE: [0] )
STOP SN4PLE: [99]
I 1
ERROR (SIGMA): [1.96] l REPEAT #: [0]
A EFFIC (%): Select value determined in III.E.
A CROSSTLK (%): Select value determined in III.C l
-__--m _______ _ _ _ - . _ . . _ _ _ _ _ _
I SOP HP-27 Rev. 3 Page 6 of 11 Appr'd 6. N.
Date /2f/f8
, A BKGND (CPM ) : Select value determined in III.E.
B EFFIC (%): Select value determined in III.E B BKGND'(CPM): Select value determined in III.E BKGD (M ) : Select time used in'III.E VOL UNITS: 10]
VOL (EA): [1]
ACTIVITY UNITS: [1]
ALARM (dpm/V): [200]
G. See HP SOP 33 for sample counting instructions.
IV. Procedure--Baird Polyspec A. Determine plateau:
- 1. Switch power to off.
- 2. Adjust switches to following positions:
- a. Scaler (1) Preset count /bs -- bs.
(2) Background subtract -- all zeros.
- b. Analyzer (1) Diff./integr. -- integr.
(2) Lower 1. -- 7
- c. Ampiifier (1) Coarse gain -- 1/32 (2) Fine gain -- 0.45
- d. Display (1) Set to scal. 1 l
l I
iI - - -
l SOP HP-27 Rev. 3 Page 7 of 11 Appr'd 6. .
Date / /
- e. Timer:
(1) Set switch to timer.
(2) Time base -- 0.1 sec.
(3) Preset time -- 10.
- f. Control:
(1) Manual / Automatic -- Manual.
(2) Off/drm -- drm.
- g. High voltage:
(1) Course H.V. -- 1.6 (Switch on back panel.
Caution: any change of this switch should be made while high voltage is in standby.)
(2) Fine H.V. -- midrange.
(3) On/ Standby -- Standby.
- 3. Switch power on.
- 4. Switch on/ standby to on.
I. 5. Place calibration source under detector: Pu-239 for alpha counting or SrY-90 for beta or alpha + beta
. counting.
- 6. Press the start button.
- 7. Increase high voltage stepwise antil scaler shows a count rate.
- 8. Decrease high voltage one step.
- 9. Press stop button.
- 10. Switch off/drm to off.
- 11. Set time base to 0.1 minute.
lI u= = . - . .
t I
SOP HP-27 _,
Rev. 3 Page 8 of 11 Appr'dg.,fk. Q Date l,)/ %f
- 12. Press start button. Take ene minute counts, increasing the hign vcltage 100 volts af ter each count, until a pla teau is reached and counts began I to increase again.
counts per minute.
Plot a curve of high voltage vs I 13. Proper high voltage setting is approximately the middle of the plateau. Record value in instrument log book.
B. Scaler test function:
- 1. 1.djust switches as described in IV. A.2 with the modifications in IV.A.10 and IV.A.ll.
- 2. Press start.
3' . Af1 u Jone minute scaler reading should be approxi-macely 7200. Record value in instrument log book.
C. Chi-square tes t:
- 1. Switen printer to on.
- 2. Place calibration source in planchet. Load planche t on lef t planchet stand and press start. When source is under detector switch planchet changer to of f.
- 3. Adjust switchen as described in IV.A.2 with the modifications'in IV.A.10 and IV.A.ll.
- 4. Press the start button, allow calibration source to count 21 times then press stop button.
- 5. The chi-square is esiculated from the following equation:
[ (ai - A)2 n
X 2.
A I
I
I SOP HP-27 _
Rev. 3 Page 9 of 11 Appr'd j . M .
Date / / @[
Where:
A = average counting rate a = counting rate observed in any counting I. interval number of observations n =
x 2= Chi-square value
- 6. For 20 degrees of freedom, a chi-square value between 11 and 27 is satisf actory. If the chi-I square value is not satisfactory, contact the Health Physics group.
P. Determining efficiencies:
- 1. Adjust switches as described in IV.A.2 with the following modifications:
- a. Timer (1) Time base -- 0.1 minute.
(2) Preset time -- 50
- b. Control (1) Manual / Automatic -- Automatic (2) Of f/drm -- of f
- c. High voltage (1) Set to value determined in IV.A
- 2. Set up automatic planenet changer as follows:
l (1) Single / Recycle -- single l
, I (2) Power switch -- on I
j g 3. Place alpha and beta calibration sources in separate
-g planchets. On the lef t planchet stand, load the sources, and an empty planchet to determine back-f ground.
i I ~- - - - - - - - - - - - - - -
33-
I- SOP HP-27 Rev. 3 _Page 10 of 11 Appr'd'g.M.
Date /d / / s.
- 4. Press start button on planchet changer.
- 5. Efficiencies are calculated from the following equation:
Efficiency = (Gross counts-Bkgd)/4 Pi Source dpm Record value in instrument log book.
3 6. If ef ficiency dif f ers f rom the previous value by g greater than 10%, contact the Health Physics group.
Previous values can be found in the instrument log book.
'E. See HP SOP 33 for sample counting instructions.
V. Procedure--Eberline BC-4 A. Cni-square test:
I 1. Load beta calibration source in planchet and close drawer.
- 2. Set count time to 1 minute.
- 3. Count source 21 times, record values.
- 4. The chi-square is calculated from the following equation:
{ (ai - A)2 n
x 2=
I A Where:
A = average counting rate a counting rate observed in any counting I
=
interval n = number of observations x
2= Chi-square value l
Y - __
't f '{,'.
i- ,
SOP HP-27 Rev.- 3 Page ll-of 11-Appr'd 8.N.
Date / //
5.' For 20 degrees of freedom, a chi-square value
- between 11 and 27 is satisf actory. If f the chi-square value is'.not satisfactory, contact the Health Physics group.,
. B. Determining efficiency:
~1. Load beta calibration source in planenet and close
-drawer.
.2. Set'. count time to 'S minutes. (
- 3. Press-. s tart. After count is complete record value-in ins trument log book-in counts'per minute.
- 4. ' Remove calibration source, close drawer and count background for 5 minutas- Record value'in instru-ment log book'in counts per minute.
- 5. Efficiency is calculated from tne following equa t. ion:
Ef ficiency = (Gross counts-bkgd)/4 Pi source dpm Record value in instrument : log book.
- 6. If efficiency differs trom previous value by greater than 10% contact Health Physics. group.
l t-1 1
L
)
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p
_ - _ . _ = _ _ _ _ _ _ _ __ _-- :- .- -- -
'la
m I SOP HP-33 Rev. new Page 1 of_5 Appr'd [ N. b _
Date /M!/!O Operation of Sample Counting Systems I. Policy Sample data that has a dir?ct ef fect on radiation risk evalua-I II.
tion shall be counted with a calibrated instrument.
Purpose The purpose of this procedure is to establish a standard method for the basic operation of the following counting systems:
A. Canberra Model 2000 Alpha / Beta / Gamma System B. Baird Polyspec Research Spectrometer C. Eberline Model BC-4 Beta Counter III. Procedure--Canberra 2400_
A. System start up
- 1. Power on
- a. ac power switch is located on rear panel.
- 2. Setup parameters NOTE: The system has a backup battery, if the parameter displayed is correct just press
[ ENTER].
- a. Set date in the form MMDDYY - [ ENTER] .
- b. Set time in the form HHMMSS -- [ ENTER] .
-I c. BARCODE(0=YES,1=NO) --
[1] --
[ ENTER] .
- d. ALT LOCATION (0=Y,1=N) --
[1] -- [ ENTER].
- e. PRESET (ALPHA =0, BETA =1) --
[0] --
[ ENTER] .
- f. SAVE DATA (0= NET,1=CONCEN) --
[0] --
[ ENTER] .
I
m:rm ..
s il
- SOP HP-33 Rev. new. Page 2 of 5 Appr'd6.k.
Date } //
- 3. Low level discriminator -- 0.06.
- 4. Flowme ter -- 0.15 to 0. 20.
- 5. Printer -- On Line.
B. Sample counting:
- 1. Place samples in planchets and load into elevator
. magazine. Place aluminum disk on top of last sample.
- 2. Lock elevator magazine in position above turntable.
Program 1 is reserved for normal. swipe counting.
3.
Programs 2-5 are available for~ other counting proce-dures. See HP SOP 27 to edit counting programs.
- 4. To start sample count press the following key pads:
[Run)
[ Program #]
[ Enter}
[ Restack]
S. Af ter samples have been counted, remove elevator magazine and discard samples.
- 6. Counting results will be printed out in gross coun ts , net counts per minute, and total activity in i disintegrations per minute.
IV. Procedure--Baird Polyspec ,
A. System start-up
- 1. Matrix printer
- a. On/ standby -- On.
L l b. Check paper feed i
' " ~ ' '
~~ ~
~ ' ' ~ '
~~
EIl.L~ _.l E ~ l' ~ T ~
SOP HP-33 Rev. new Page- 3 of.5
- Appr'd d M.'
Date /E / -
- 2. Polyspec
- a. High Voltage Function (1) 1.6'or 3.0 KV range -- red' light.-
(2) Set desired voltage. JResu'lts of. previous voltage check are in the instrument log book.- (See HP SOP 27.)
(3). On/s tandby -- Standby.
- b. Scaler
'(1) Tes t swi tch -- Of f .
(2) -psc/bs -- bs.
(3) Preset background subtract thumb wheels to appropriate reading'for Beta counting.
Results of the previous background check are in the instrument log book. (See-HP SOP 27.)
(4) Preset background to 0 for Alpha counting.
- c. Analyzer (1) diff/integ -- integ (2) lower 1. -- 7 (3) window -- 99
- d. Amplifier
'(1) coarse gain.-- 1/32 (2) fine gain -- 0.45 l e. Display L
(1) Set at scal. 1
g I t
l SOP HP-33 Rev. new Page 4 of,5 Appr'd 6. .
Date /d2 /
- f. Timer (1) Set time base for desired time (0.1 I minutes for normal swipe counting).
(2) Set preset time for desired time (000005 minutes for normal swipe counting).
(3) Set dial on sample number.
- g. Control (1) manual / automatic -- automatic (2) off/drm -- off (3) POWER SWITCH ON (red light)
- 3. Automatic planchet changer (1) single / recycle -- single (2) POWER SWITCH ON (red light)
(3) Gas flow -- adjust needle' valve on regula-tor so flow is approximately one bubble per second.
- 4. Switch On/ Standby to ON B. Sample counting
- 1. Load samples in the lef t planchet stand. ~ {
- 2. Press start button on planchet changer.
- 3. Samples will automatically return to the lef t )
planchet stand when counting is complete.
- 4. Always leave one empty planche t on the changer when 1 counting is complete.
- 5. Counting information will be displayed on scaler and printed out in gross counts.
I l l
l 1
SOP HP-33 Rev. new Page 5 of 5 Appr'd 8.
Date /fQ //8
- 6. Total sample activity can be obtained by dividing l
the gross counts by the ef ficiency. Efficiency values are in the instrument log book.
V. Procedure--Eberline BC-4 A. System start-up
- 1. Turn POWER switch ON
- 2. Set MODE switch to TIMED
- 3. Set COUNT TIME IN MINUTES switch to desired count I B.
time (1 minute for normal swipe counting).
Sample counting
- 1. Pull sample drawer out and load sample into planchet, close drawer.
- 2. Push RESET-START switch.
- 3. COUNTING indicator (red light) and scaler will turn on.
- 4. Instrument will stop counting af ter preset time and scaler will display total count.
- 5. Total activity of sample can be obtained from the total count by subtracting background and dividing by the efficiency. Background and efficiency values I- are in the instrument log book.
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