ML20082L417
| ML20082L417 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 06/30/1991 |
| From: | Mckibben J, Meyer W MISSOURI, UNIV. OF, ROLLA, MO |
| To: | Weiss S NRC |
| References | |
| NUDOCS 9109040106 | |
| Download: ML20082L417 (189) | |
Text
4 e .
II Research Reactor Facility UNIVERS0Y OF MISSOURI Roscarch Park August 27, 1991 Columbia Missouri 65211 Telephone (314) 882 4211 Fax (314)882 3443 Seymour H. Weiss, Director U. S. Nuclear Regulatory Commission PDNP M.S. I1-E 20 Washingtc:1 D. C. 20555 REFERENCft: Docket 50-186 University of Missourt Research Reactor License R-103
Dear Sir:
l Enclo.6ed are two copies of the Reactor Operationc Annual Report for the Ur lversity of Missouri Research Reactor, The reporting period covers 1 < July 1990 through 30 June 1991.
If you have any questions, Please feel free to call.
O iSincerely (s
Walt A. Meyer, D
Reactor Manager Enclosure (2) xc: w/ report: U.S. N.R.C. W~
c/o Document Control Desk
- l. Washington, DC 99109040106 910630 PDR R.
ADUCK 05000186 POR COLUMBIA KANSAS CITY ROLLA an equal opportunity institution ST. LOUIS p
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UNIVERSITY OF MISSOURI I UNIVERSITY OF MISSOURI g RESEARCH REACTOR I
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l I OPERATIONS ANNUAL REPORT I 1990 - 1991
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I gy&~p i at >;m I $x@/kg 8Y i _ _ _ _ _
UNIVERSITY OF MISboURI RESEARCH REACTOR FACILTIY REACTOR OPERATIONS ANNUAL REPORT AUGUST 1991 i-i f
i Compiled by the Reactor Staff i
e
- q. Submitted by /
i Walt A. Meyer, r.
- Reactor Manager .
Reviewed and Approved
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,/(n_,,6 b7% ; &y'p/' , s.,
i V -J, C. McKibben Associate Director i
- -. - ,-n- ,- , . . -, ..r,-
l TABLE OF CONTENTS i
Section Pace Number
- 1. REACTOR OPERATIONS
SUMMARY
I-l through I-10
- 11. CHANGES TO MURR PROCEDURES 11-1 through 11-7 A. STANDARD OPERATING PROCEDURES B MURR SITE EMERGENCY PROCEDURES
& FACILITY EMERGENCY PROCEDURES C. HEALTH PHYSICS STANDARD OPERATING PROCEDURES IIL REVISIONS TO THE HAZARDS
SUMMARY
REPORT 111-1 through 111-11 IV. PLANT AND SYSTEM MODIFICATIONS IV-1 through IV-3 V. NEW TESTS AND EXPERIMENTS V-1 through V-2 VI. SPECIAL NUCLEAR MATERIALS ACTIVITIES VI-l through VI-2 Vll. REACTOR PHYS!CS ACTIVITIES VII-1 through Vll-5 Vlli.
SUMMARY
OF RADIOACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT Vlli-I through Vill-2 IX.
SUMMARY
OF ENVIRONMENTAL SURVEYS IX-1 through IX-8 X
SUMMARY
OF RADIATION EXPOSURES TO ,
FACILITY STAFF, EXPERIMENTERS. AND VISITORS X-1 through X-3 11
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SECTION I i l
REACTOR OPERATIONS
SUMMARY
l 1 July 1990 through 30 June 1991 1 The following table and discussion summarize reactor operations in the period 1 July 1990 through 30 June 1991.
Evil Power Percent Date Full Power Hours Mett awatt Days of Total Time of Schedule
- July 1990 670.34 279.52 90.10 100.91 Aug. 1990 696.33 290.24 93.59 104.82 Sept.1990 649.75 270.83 90.24 101.07 Oct. 1990 662.40 276.13 88.91 99.58 Nov. 1990 652.84 272.10 90.67 101.55 Dec. 1990 678.89 283.00 91.25 102.20 Jan. 1991 684.75 285.40 92.04 103.08 Feb. 1991 593.73 247.70 88.35 98.96 Mar. I991 692.96 288.81 93.14 104.32 Apr. 1991 -640.I1 266.86 89.03 99.71 May 1991 685.49 285.76 92.14 103.19 June 1991' 669.20 278.94 92.94 104.10 Total for Year 7,976.79 3.325.29 91.06 % of 101.99 % of Time for Yr. Sched. Time for at 10MW 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 fifteen unscheduled chutdowns recorded during the year 1 July 1990 through 30 June 1991. This number is half of the unscheduled shutdowns for the prev.ous reporting year. The small number of spurious unscheduled shutdowns can most likely be attributed to the conclitioned power supplied to reactor instrumentation by the Uninterruptible Power-Supply (UPS) installed in 1989. Of t'Te unscheduled shutdowns, six were Rod Run-Ins (RRis) and nine were scrams.
Seven of the unscheduled shutdowns (1 RRI and 6 scrams) were due to a Nuclear Instrument drawer detector or cabling failure generating a spurious shut down signal (no actual high power or short period was 1-1
indicated). In April 1991, the University sent out a bid package for replace-ment of the Nuclear Instrument (NI) System. The replacement of the Nuclear Instruments is being supported by DOE funding for University Research Reactors (URRs). The University anticipates that replacement of the NI System and the use of integrated cable detectors will solve the spurious scram problems associated with Nis.
Of the remaining eight unscheduled shutdowns, five were due to personnel error and three were initiated by the duty operator in order to repair equipment.
July 1990 The reactor operated continuously in July with the following excepuons: five shutdowns for scheduled maintenance and refueling; and three unscheduled shutdowns.
On July 8, a rod run-in occurred for which no apparent cause was determined. All nuclear instrument chart indicadons were normal. No abnormal indicadons were noted on any other instrumentation. The rod run-in was subsequently reset and full power was restored in approxi-mately three minutes.
On July 12 an intermediate range monitor (N.I. channel #3) short period scram occurred. No actual power increase or short period was indicated on any instrumentation. The cause was felt to be a failed detector for channel #3. The detector was replaced and tested satinfactorily and the reactor was refueled and returned to normal operauon.
On July 21, an intermediate range monitor (N.I. channel #3) short period scram again occurred. No actual power increase or short period was indicated on any instrumentation. Electronics technicians tested the detector and drawer components for this channel and found no anomalies.
The voltage regulator was replaced to eliminate the probability of it being a causauve factor. On the next maintenance day, electronics technicians discovered a fuse in the drawer, that was not securely in place, which may have caused the two previous unscheduled shutdowns.
Majo maintenance items for this month included: Installing aluminum and sulfur filters in Beamport "F" centertube; replacing inter-mediate range channel #3 detector; replacing the voltage regulator in channel #3 arawer; replacing the control circuit transformer on exhaust fan 14; installing Modification Package 90-2. which changed the secondary 1-2
i pump control circuitry to allow P-4 tostart and run automatically while one main secondary pump is running to provide sufficient cooling flow for the air
. conditioning unit.
6.ugust 1990 The reactor operated continuously in August with the fallowing .
exceptions: four shutdowns for scheduled maintenance and refueling.
There were no unscheduled shutdowns this month.
August 15 through August 17, the Nuclear Regulatory Commission I j
perfornaed an unannounced Safety inspecuan (90-001) of the reactor, specifically inspecting reactor operations, health physics, and transportation l activities.
Major maintenance items for the month included: removing the iron filters from Beamport "F" centertube and installing silicon filters; renewing
.the coils in relays R3A and R3B (evacuation and isolation system).
September 1990 The reactor opera;ed continuously in September with the following excepuons: four shutdowns for scheduled maintenance and refueling.
There were no unscheduled shutdowns this month.
With the reactor shut down during the September 4 schedaled maintenance day, the reactor operators determined that they could not maintain anti-siphon system pressure during the primary system startup sequence The problem was quickly isolated to leakage past one of the anti-siphon (543) valves, After pumping the pool down to the level of these-valves, a coupling pin in the valve actuator linkage was discovered missing on valve 543B, rendering it inoperable.
l Anti-siphon valves 543A and 543B are redundant, solenoid controlled, l air operated, four inch valves which, when operated by a signal from core l ' discharge pressure transmitters 944A and 9448, will open and inject air from a storage tank into the inverted loop (discharge) leg of the reactor core. This system is designed to displace an amount of water in the outlet -
leg which will break a siphon in the event of a double ended pipe rupture.
l allowing the core to remain covered with a minimum of six feet of water.
l_ The operation of either valve (543A or 5438) will allow the system to function. .There was no indication of V543B leaking during the previous 1-3 l
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week's operation so the coupling pin on valve 543B apparently failed after the scheduled reactor shutdown, either when the valve.was opened as part ,
- of the nonnal primary system shutdown sequence or when the valve was cycled as part of the normal primary system startup sequence. The coupling pin.was replaced and secured with a ring keeper at both ends. The
- operability and pressure integrity of the valve was tested satisfactorily. The similar pin in the valve actuator linkage for valve 543A was also checked.
The reactor was then returned to normal operation.
Major maintenance ittems for the month included: removing the bismuth filter and cadmium disk from Beamport "F" centertube: replacing the pin on the lower linkage coupling to anti-siphon valve 543B: removing
- depleted poolidelonizauon bed "U" and loading new deionization bed "R": ,
replacing the secondary water make up valve; and installing a new secondary coolant monitor.
October 1990 The reactor operated continuously in October with the following exceptions: five shutdowns for scheduled maintenance and refueling; and one shutdown for a flux trap change. There were no unscheduled shut-4 downs this month.
Major maintenance items for the month included: reinstalling the (Rosemont) secondary flow detector: completing the biennial changeout of control blade offset mechanism "D": removing the Si filter and instalhng the
- Fe/Al/S filter in the centertube of Beamport "F".
November 1990 The reactor operated continuously in November with the following exceptions: .four shutdowns for scheduled maintenance and refueling: and three unscheduled shutdowns. -
On November 12. two spurious reactor scrams occurred while shifting the channel #4 Nuclear Instrument wide range switch upscahi during
- normal startups. After the first shutdown, the wide range monitor range switch was cycled several Umes and a reactor startup was commenced.
After the second shutdown. electronics technicians used a current source to simulate input- to the wide range monitor (Nuclear Instrument channel #4).
but could not reproduce the spurious scram problem. The range switch was removed and cleaned and the channel #4 detector cable resistance was checked. The switch was reinstalled and anor' er attempt to reproduce the problem was unsuccessful. The cause was suspected to be either a sticking 1-4
, relay contact in the feedback network of the picoammeter module for Nuclear Instrument channel #4 or a momentary open in the wide range monitor switch contacts during switching. The range switch was cycled through its full range and the picoammeter relays operated normally. A third normal startup was commenced. With the reactor still subertucal, a spurious channel #3 (intermediate range monitor) period scram occurred coincident with receiving a primary conductivity annunciator alarm. There was no actual period or power increase indicated on any instnunentation.
This problem was traced to faulty channel #3 cables. The detector and cables were replaced and tested and a normal startup was completed with no further problems.
Major maintenance items for the month included: performing preventauve maintenance and testing on electrical substations A and B and motor control centers 1, 2A, 2B. and 5 and the 208 volt distribuuon center; replacing the DC amplifier in N.I. channel #6 (power range monitor);
replacing the motor for the facility supply air fan (SF-1); replacing the detector and cables for N.I. channel #3 (intermediate range monitor); and replacing the 115 VAC annunciator fuse.
December 1990 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and refueling; and one unscheduled shutdown.
On December 5, a pool recirculaung loop low flow scram was initiated by pool flow detector 912D. No actual low pool flow condition was indicated on any instrumentation. An operadonal compliance check performed on th's How detector indicated that some air was entrained in the sensing lines.
The air in the sensing lines was thought to be the cause of this spurious scram. A scram check was performed and found to be in compliance. The air was purged from the sensing lines and a complete compliance check was performed satisfactorily. On the previous maintenance day (12-3-90), the semi-annual compliance check was performed on this flow detector (912D).
At that Ume the operator working with the detector indicated he was having a difficult time keeping air out of the tygon tubing connecung the MURR tesung rig and the flow detector. This compliance check was completed satisfactorily but it was at this time that air may have been inadvertently introduced into the flow detector sensing lines. The operations stalT have been reminded of the importance of ensuring that no air is introduced into the sensing lines of this detector type during maintenance activities.
1-5
l The annual facility emergency plan drill was held on December 10. An NRC inspection for emergency training and preparedness was performed from December 17 through December 21,1990.
Major maintenance items for the month included: completing modification package #88-1 which re-directs the discharge flow from secondary pump #4 to the southeast bay of the cooling tower when the reactor is shut down.
January 1991 The reactor operated continuously in January with the followir
- cxceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdown.
On January 21, a spurious reactor scram occurred while the reactor was suberitical during a nonnal startup. The scram was caused by an electrical surge that occurred when an electronics technician accidentally created a short circuit condition while installing an upscale switch on the new bridge area radiation monitor.
The Reactor Operauons Engineer had given the electronics technician permission to complete this maintenance item. Following a review with the Reactor Manager, it was decided that this type of maintenance will not be attempted when the reactor a operating.
Major maintenance items for the month included: performing maintenance on electrical substations A and B: sending a radioactive waste shipment to Barnwell South Carolina: dumping depleted pool DI bed "E" and loading new pool D1 bed "W": reld incorporating control of the containment isolation back up doors into relays 2KIA and 2KlB as part of Modification Package 88-4.
February 1991 The reactor operated continuously in February with the following exceptions: three shutdowns for scheduled maintenance and refueting: four unscheduled shutdowns.
On February 4 a manual rod run-in was initiated when the reactor operator noticed oscillation of the period and level indications for intermediate range monitor (IRM) channel #3. The reactor was subcritical during a normal startup when the rod run-in was initiated. No period or 1-6
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. power fluctuations were noted on any other nuclear instrumentation; 1 Electronics. technicians replaced the compensating voltage power supply on channel IRM #3 and the instrument was tested satisfactorily. A nonnal startup was then completed with no further problems of this type.
- On February 11 a spurious channel #4 (wide range monitor) high ,
power scram occurred while shutting down the reactor by manual rod run-in for scheduled maintenance day activities. The scram occurred approxi-mately onc .ninute after initiation of a scheduled manual rod run-in while ,
shifting the wide range switch downscale. Indicated reactor power at the !
time was estimated to be approximately one megawatt. No actual high power condition was indicated on any instrumentation. The cause was felt to be related to the wide range switch, but attempts to duplicate the problem were unsuccessful, The switch was examined and tested satts-
- factorily and no anomalies were indicated.
On February 15, a manual rod run-in was initiated after the reactor operator detected a blown fuse indication for the annunciator 115 VAC power supply. Electronics technicians discovered a grounding problem between a tenninal board ano the fuel vault alarm annunciator circuit. A lead had been pinched between a stand-off holding a relay and the metal cabinet, degrading the lead insulauon to a point where the reduced 1
resistance to ground allowed enough current to be drawn to blow the fuse.
The lead was repaired and repositioned, and the ground was cleared. The
' fuse was replaced and the annunciator was tested and determined to be functioning normally.
On February 25. a rod not in contact with magnet rod run-in occurred when control blade "D" disengaged from its magnet. This occurred at the same time that an operator was attempting to return a silicon tube to its normal irradiation position in the re cor reflector. region, which is in close proximity to the counter balance arm for control blade "D". It is possible that the operator handling the sample inadvertently bumped the counter
- balance arm with the silicon tube, causing the control blade to separate from its magnet. The control blade drive housing, the anvil surface and magnet were inspected and no anomalies were found, Major maintenance items for the month included: replacing the compensating voltage power supply on intermediate range monitor channel
- 3: installing and testing satisfactorily, a new centertube design in Beamport "F" (Amendment to RUR 228); completing the installation and testing of the l-7
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new area radiation monitoring system (ARMS) and disconnecting the old
. ARMS.
- March 1991 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and refueling; and two unscheduled shutdowns.
On March 13, a reactor scram occurred after the inadvertent move.
ment of the master control switch from the "on" to the " test" position. The switch _was accidentally bumped by a clipboard that the console reactor _;
operator was using to take logs. Operators have been cauuoned to minimize or eliminate extraneous material from the control console desk and to be more careful when operating near sensitive equipment switches.
On March 18. a manual rod run-in was initiated several minutes into a nonnal reactor startup when the reactor operator detected oscillations in a primary heat exchanger temperature indication (9808), Earlier that day,
~
electronics technicians had completed a compliance procedure on primary RTD 980B _which involves disconnecting the RTD from its transmitter, it
- appears that the RTD may not have been reconnected satisfactorily following completion of the. compliance procedure, although the reconnection procedure incorporates a double check of the reconnection by a licensed operator.
~ _The electronics technician loosened and retightened all connecuons between the RTD and its transmitter and the oscillations disappeared. The-RTD and temperature transmitter were tested.for temperature response
_ prior to this second reconnection by electronics technicians, The RTD and temperature transmitter followed temperature changes over the range-that temperatures were varied, with the only deviation being that the tempera-ture indication oscillated 1 to 1.5 each side of the test temperature instead of providlag a stable temperature. Because of the conservatively set
- operational scram setpoints on primary inlet water t'emperature (147.5 for -
980B), this~ instrument would have provided its necessary safety trip function in a range of temperatures,146 F to 149 F, which is well below the technical specificadons limiting safety setpoint setting of 155 F (maximum).
The temperature verification of the 980B was completed after the second reconnection and a normal reactor startup was completed satisfactorily.
4 1-8
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L Major maintenance items for the month included installing the supplementary fuel storage basket.
April 1991 1
The reactor operated continuously in April with the following j exceptions: five shutdowns for scheduled maintenance and refueling; and i one unscheduled shutdown. l On April 25 a rod not in contact with magnet rod run-in occurred when control blade "D" disengaged from its magnet. The control rod separated from the magnet when the offset mechanism counter balance arm was inadvertently bumped by a silicon tube that was being handled in the reflector region by an operator. The operator involved was instructed to chan7 his handling procedure to minimize the possibility of this recurring.
Major maintenance items for the month included: replacing the meter relay trip unit for pressure transmitter 917: replacing the MV/l for the in-pool heat exchanger 4T indication: removing offset #6 from position "A" and replacing it with offset #8.
May 1991 The reactor operated continuously in May with following the exceptions: four shutdowns for. scheduled maintenance and refueling. .
There were no unscheduled shutdowns this month.
The annual containment building leak rate test required by Technical Specification 5.1 was conducted using the makeup flow method on May 13, 1991. The leak rate was determined to be 8.9 ft3/ min, with an over pressure of one pound per square inch gauge. This is well below the Technical Specification 4.2.c limit of 16.3 ft3/ min.
Major maintenance items for the month included: dumping depleted pool'defonization bed 'V" into drying barrels; loading, and placing on service, new pool delonization bed "P": and completing the annual containment building leak rate test.
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June 1991 The reactor cperated conunuously in June with the following i exceptions: four shutdowns for scheduled maintenance and refueling.
There were no unscheduled shutdowns this month.
A Nuclear Regulatory Commission inspecuan team conducted an exmnination of MURR security and Special Nuclear Material Accountability on June 20, 21 & 22, 1991.
W i-p 5
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4 SECTION 11 1 July 1990 through 30 June 1991 A CPANGES TO THE STANDARD OPERATING PROCEDURES, 2nd Edition Effective Date: 5/02/89 (Revisions #1 through #24 to the October 1981 printing ,
were incorporated.) l 1
As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following. 1 l
Resiston No. 3, dated 10/18/90 l Revision No. 4. dated 4/30/91 Revision No, 5 dated 6/27/91 a CHAINGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES (dated January 1985, and revised May 13,198P; NOTE:' New manual printed May 13,1988 As required by the MURR TechnicM Specifications, the Reactor Manager reviewed and approved the following:
Revision No. 6 dated 7/11/90 Revision No. 7, dated 4/8/91 NOTE: SEP-7, page 2: Social Security Numbers have been omitted per request by Nuclear Regulatory Commission Al Adams, 9/87.
C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES NOTE: New manual issued 10/29/90 Preface, dated 10/90 HP-18. Redston No. 3 dated 1/12/91 HP37, dated 10/8/90 HP-38, dated 10/8/90 The revisions to the Standard Operating Procedures, MURR Site Emergency Procedures / Facility Emergency Procedures, and Health Physics Standard Operating Procedures are contained in this section with the part of'each page that was revised marked on the right side of the page by a bracket ( l ).
II-1
STANDARD OPERATING PROCEDURES 2nd Edition, Effective Date: 5/02/89
- - - (Revisions #1 through #24 to the October 1981 printing were incorporated.)
Revision Number 3 Revision Date: October 18,1990 Pace Number Page Number SOP /I-2 SOP /Vil-12 SOP /1-3 SOP /VII-20 SOP /I-4 SOP /Vil-22 SOP /1-I l i SOP /1-16 SOP / Vill-2 SOP /l-17 SOP / Vill-7 SOP /1-18 SOP / Vill-12 SOP /l-19 Reset SOP / Vill-19 SOP /1-20 Reset _ SOP / Vill-43 New-SOP /1 Reset SOP / Vill-44 New SOP /1-22 : Reset SOP / Vill-45 New SOP /I Reset SOP / Vill-46 New SOP /1-24 New-SOP /A-la SOP /II-9 SOP /A-lb SOP /II-16 ~ SOP /A-Ic SOP /A-1d SOP /Ill-1 SOP /III-2 SOP /A-8a SOP /A-8b SOP /VI-6 SOP /A-8c SOP /VI-7 SOP /VI-9 SOP /A-11a SOP /VII SOP /A-20a New
. SOP /VII-3 SOP /A-20b New SOP /VII-4 SOP /A-20c New
. SOP /VII-1 O ~ SOP /A-20d New SOP /Vil-11 Il-2
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11.4L Administrative Policies 1.4.1 Standing Orders New procedures prior to becoming part of these Standard Operating Procedures, procedures to be in effect for a _short period, and special instrucuons relating to operation of the ]
reactor, will be issued as Standing Orders. All effecuve Standing Orders, as well as a-listing of current orders, will be maintained in >
a log in the reactor control room. Standing Orders that are no longer applicable or that are incorporated into the Standard Operating Procedures will be cancelled and removed from the log.
All Standing Orders will be approved by signature of the Reactor Manager or his authorized delegate.
1.4.2 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 operation.
The Shift Supervisor is the Reactor Manager's delegated representative on shift and is given the authority to direct the actMties (both _lleensed 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 actMties-during the Shift Supervisor's absence.
Any . SOP reference to Shift Supervisor applies to the lead Senior Operator when'the Shift Supervisor is absent from his duty shift.
Rev. 10/18/90 App'd W SOP /I-2
~ _ _ _ _ _
C Operating Crews
.1. The minimum number of reactor operators for reactor opera-l tion will be two licensed persons. One of these will be licensed ,
as a Senior Reactor Operator. One exception is allowedfor l :
family emergencies. -In this case, one Senior Reactor Operator l' l may operate the rcactor with another knowledgeable person l present in the facility, which exceeds Technical Specipcation ) ?
6.1.i requirements. This mode ofoperation shall be docu- ) \
mented in the console log and minimized by calling in an )
additional licensed operator. The Reactor Manager or )
Operations Engineer should be informed as soon as possible. )'
- 2. There will be one licensed operator in the control room at all ).
times whenever the reactor is not considered secured, as defined )
in Part 1.20 of the Technical Specifcations. 'When the reactor is ) ,
shut down but not secured, the control room boundanJ can be i expanded to include the bridge area during refueling or main- ) ~
tenance activities. l .
- D. Console Loc A-log will be maintained in the control room by the reactor operator providing a detailed diary of reactor operation.
l E. Corrections to console log. Nuclear and Process Data and Routine Patrol Sheets Any corrections to a log entry or data sheet will be done by a single
'line through the incorrect entry, plus the initials of the person iking the change. If the correction is made at a later date, the person making the correction will initial a_nd date the change.
-F. Changing Reactor _ ReactMty Operations affecting changes in core reactMty, other than normal steady' state power control. i.e. refueling, startup, etc., will be directly-supervised by a Senior Operator.
G. 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 is authorized. la the absence of the Shift Supervisor from the control room, to place the Rev. -10/18/90 App'd \#6TT\ SOP /I-3
reactor in a safe shutdown mode if he deems it necessary. It is-important that the reactor systems, while the reactor is critical, not be experimented with, or reactor control systems tested, unless permission to do so is explicitly granted by either the Reactor Manager or his designated representauve.
H. Maintenance _ Performed on Reactor Systems All maintenance on reactor and license related systems and equipment will be reviewed by the Shift Supervisor to ensure ] i operabil_ity of these systems prior to reactor operadon.
I, Maintaining Acuve Operator Status Actively performing the functions of an operator or senior operator
- means that an individual has a posidon on the shift crew that requires the indMdual to be licensed as defined in 10 CFR 55, and that the indMdual carries out and is responsible for the dudes 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 actMties, 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 direcuon of a Senior Operator before returning to active status, J. Reactor Operating Parameters The reactor shall-be operated in strict accordance with the Reactor License R-103 and the operating limits in Tables III and IV. .
1.4.3 Startup A. Startup Following a Scram i
Tne reactor will not be started up following a scram until the cause of the scram has been determined and safe corrective action taken.
If, after thorough investigation, the cause of the unscheduled reduction _in power cannot be determined and all systems are found to be normal, the reactor may be started up with the approval of the Reactor-Manager or his authorized delegate.
Rev. 10/18/90 App'd IM SOP /I-4
IL During reactor operation the control room shall be
. occupied only by persons authorized by the Reactor Manager or Shift Supervisor.
1.4.5 Shutdown A- Shutdown operations will be accomphshed under conditions designed to assure safety of the reactor and personnel.
B Shutdown of the reactor will be in accordance with approved procedurcs.
- C Conditions causing automatic shutdown of the reactor
- will be investigated as to cause, and corrective action a taken prior to restarting the reactor.
D. Unscheduled shutdown sheets will be filled out for all l unplanned rod run-ins and scrams that occurred while :.t 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 SOP (HP-2).
- Specific except!.ons to this inchide the beamport foor .)
- procedures apply, l 1 F. The Shift Supervisor shall have a shutdown checksheet I performed if the control room will be unattended for an
- i. extended period of time, j
- 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.
V L4.6 Experiments -
i i A The Reactor Manager will have operating authority over all experiments performed within the reactor
- containment or which may affect reactor operations.
t 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 i control room of any activity which may affect reactor
) operation.
- Rev. 10/18/90 App'd QCP\ SOP /I-11
l.
1.4.9_ Radiation Safety The Shift Supenisor 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 conducted under his supenision. Radiation safety is a very important part of this responsibility. It should not be construed that surveys, monitoring, or other measurements to check for contamination or radlauon are to be made by operations personnel, but rather that the Shift Supervisor is responsible to insure that through coordination with the Health Physics personnel, adequate protection is provided for evolutions conducted during his shift.
I.4.10 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.
I,4.11 Equipment Tagout Procedure I.4.11.1 Purpose The purpose of the tagout system is to prevent injury to ~
personnel and/or damage to equipment. 1 1.4.11.2 Types of Tags A. Red Tags Red tags will be used to identify equipment which, if I operated. could present a hazard to personnel. The tag ]
will also contain information pertaining to the reason for ]
the tag. ] ,
Rev. 10/18f90 ,, app.d IMh') SOP /I-16
R Yellow Tags Yellow tags will be used to identify equipment which, if operated, could present a hazard to that or other 1 equipment. The tag will also contain information 1 pertaining to the reason for the tog. 1 1.4.11.3 Equipment Tag Out A. Tag Out Log
- 1. The tag out log will be maintained in the control room by the on duty shift supervisor.
- 2. The tagout log will be made up of six sections: I
- a. Monthly Audit i
- b. Tag Out Instructions I
- c. Index Record I
- d. Active Tag Out Sheet Section l
- e. Inactive Tag Out Sheet Section i
- f. Blank Sheet Section 1 a Performing a Tag Out
- 1. A tag out will be performed byfacility personnel I with the approval of the on duty sht) supervisor. )
- 2. The on duty shift supen'isor must approve the 1 hanging or removal of ALL tags. 1
- 3. In the event that a tag is discovered missing, the ]
shift supervisor will be informed immediately. 1 The shift supervisor will determine corrective )
action. 1 C Tag Out Audit A tag out audit will be performed monthly as I scheduled by a predetermined DUE DATE. The .)
person performing the Audit will: 1
- 1. Inventory all active tags. 1 L Note any incorrect or missing tags. 1
- 3. Sign and date the monthly Audit sheet. )
- 4. Discard the old inactive tag out sheets, l Rev 10/18/90 App'd bNT^ SOP /1-17
1 l
Ml]RR TAG OUT INSTRUCTIONS )
Tag Out: )
- 1. Obtain the shtft supervisor's permission to hang tag (s). }
- 2. Complete the MURK Tag Out index Record. For tag out )
use next sequential number (sc{f explanatorJ). )
- 3. Complete both sides of the MURR Tag Out Sheet (self )
explanaton)). }
Tag Removal: }
- 1. Obtain the shift supervisor's permksion to remove tag (s). )
- 2. Complete the MURR Tag Out Sheet (move to the inactive l section if all tags are cleared). )
- 3. If all tags are cleared. complete the MURR Tag Out Index )
Record. )
New 10/18/90 App'd hwm SOP /1-18
.- . -_ _ . . - . _ _ _ _ _ _ _ . _ . _ . _ . _ _ . _ . . _ . _ _ _ . . ~ _ _ _ . . . _ . . ~ _ _ _
. Table 111 Normal Reactor Operaung Ranges
. Parameters Normal Operating Range Units
-5%
- 3. Primcry Coolant Flow, 5 MW Operation 1850 50 gpm Primary Coolant Flow,10 MW Operation 3700 50 gpm
- 4. Reactor Outlet Coolant Temperature 136 'F
- 5. Reactor Inlet Coolant Temperature 120 *F
- 6. Pressurizer Pressure 67 3 psig
- 7. Pressurizer Level CENTERLINE + 4 to -8 inches
- 8. Pool Coolant Flow, 5 MW Operation 600 100 gpm
' Pool Coolant Flow,10 MW Operation 1200 100 gpm
- 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 Rey 10/18/90 App'd NW SOP /1-19 ]
Reset
1 l
Table IV l Nominal Values of Trip Setungs for Alarm. Run-in and Scram Conditions for 10 MW Operation Scram Run-In Alarm Units
- 1. Short Period 9 11 --
sec
- 2. Low Count Rate -- --
<l.0 cps
- 3. High Power 119 114 --
% full power
- 4. RC Inlet Temp 148 --
140 #F
- 5. RC Outlet Temp 168 --
160 F
- 6. RC System Low Flow 11725 --
1800 gpm 10 MW Operation
- 7. Heat Exchanger Low 31675 -- --
gpm DP (DPS 928A/B)
- 8. Rx System Low Press 263 -- --
psig Switch PS 944A/B
- 9. Core Low AP,10 tlW 33300 -- --
gpm
- 10. Low Pressurizer Level 13 below C.L. --
10 below C.L. inch
- 11. High Pressurizer Water -- --
14 above C.L. inch Level l
Alarm and Scram received from either loop 2
Pressurizer pressure with normal system flow 3
AP Corresponding to this flow value I
Rev. 10/18/ 90 App'd WW\ SOP /I-20 l Reset
l TABLE IV (continued) .
- Scram Run-in Alarm Units 12.- Low Pressurizer Press 63 --
65- psig1
- 13. Hi Pressurizer Press 78 --
75 psig
- 14. Pool Low Flow,10 MW 490 --
530 gpm
- 15. Pool Hi Temp -- --
115 F
- 16. Low Pri Demin Flow 42.5 gpm
- 17. Low Pool Demin Flow --- --
42.5 gpm
- 18. Bldg ~ Air Plenum Hi 10 x normal oper- . -- --
mr/hr Activity ating background ,
J
- 19. Reactor Bridge 10 x normal oper- -- --
mr/hr ating background
- 20. _ RC Hi ConductRity -- --
2.0 mhos
- 21. PC Hi Conductivity -- --
2.0 mhos
- 22. Hi- Refl AP.- 10 MW 7.0 psi
~
- 23; Low Refl AP,10 MW 3.0 psi
- 24. Low N2 System Press --
1-15 psig
- 25. Low Seni Trench Level -- --
5 feet
- 26. Hi/Lo Level in T-300 - -- --
6200/2500- gal
- 27. Hi/Lo Level in T-301 -- --
6000/<100 gal Rev. 10/18/90 App d _{JAK - sopf]_21 }
Reset
e TABLE IV (contJnued)
Scram Run-in Alarm - Units
- 28. Fission Product -- --
200 cps =
Monitor Hi ActMty
- 29. Off-Gas Hi Activity _ s see below cpm
- 30. Secondary Coolant -- --
10 cps Hi ' Activity
- 31. Anti-Siphon Line Hi --
56 --
inches Level (above valves) 32 Pool Level Low >24' >28' --
feet
- 33. Reg Blade --
< 10% or <20% or ->G0% %
bottomed - withdrawn -
- 34. Vent Tank Low Level --
7-11 --
inches (below C.L.) ]
' 35. Secondary Coolant --
<1800 gpm Low Flow
- 36. Ch 4, 5. or 6 Downscale --
<95 % full-scale 37; Valve 546 A or B --
off closed
- 38. - Valve 509 off open - -- -- +
39.- Valve -547 off open
- 40. Valves 507 A/B off open --
closed with P501 on 141. Valve' S -- --
90% open or' --
90% shut
- 5 This setpoint is determined by the semiannual calibration.-
Rev; 10/18/90 Appd hh sop /[-22 l Reset i'_ ____,__u___---,r ,.-r_ , v +
, _ - - . . . - .- .. ._ _ . - . _ _ _ _ _ . . _ . _ _ . . . _ . . - . _ . . _ _ - _ . _ - _ . _ _ _ . _ _ . ~ . _
i TABLE IV (continued)
Scram ' Run-In Alarm Units-S
- 42. Nuclear Instrument inoperative --
anomaly --
- 43. Anti-Siphon System -- -
30 psig Pressure Low
)
Anti-Siphon System -- -
44 psig Pressure High
.44. Thermal Column Door - --
open --
- 45. Truck Entry --
door seal -- --
deflated
- 46. ' Evacuation or manual / auto --
manual / auto --
Isolation
- 47. = Rx System Low . 3 63 -- --
psig Pressure (PT-943) 3 Pressurizer Pressure with normal system flow 6
Any channel will scram on NI Inoperative except SRM Rev.10/18/90 AppVI ROM- '
SOP /I-23 ]
Reset
i i
THIS PAGE INTENilONALLY LEFT DIANK
+
New 10/18/90 App'd (WTA SOP /1-24
11.2 Fuel Handling Procedure 11.2 . 1 General :
A All fuel transfers will be authorized by the Reactor Manager or his designated representauve. .
H If a fuel assembly is determined by the Shift Supervisor to be damaged, authorizauon 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 movemot procedure anytime fuel is handled.
D, Containment integrity is required any time irradiated fuel is being
=
handled.
E. Fuel, new or irradiated, shall only be handled one elemenc 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 operaung.
G. Health Physics coverage shall be established whde the poolis i being lowered below normal operaung level and as deemed 1 necessary whde the pool remains below normal level. A Health )
Physics' survey shall be donc prior to inspectl.g irradiated fuel or i handling suspected ruptured irradiated fuel, and concrage wdl I continue as needed throughout these evolutions. Heal'h Physics I shall ms.titor the shipping of irradiated fuel )
H. One Senior Reactor Operator and one Reactor Operator must be present to handle fuel. Only a Senior Reactor Operator, a Reactor Operator, a Reactor Operator trainee, or Auxiliary Operator under the dirrett supervision of a Senior Reactor Operator may handle fuel.
The Auxiliary Operator will assist in fuel handlink nuly to th extent of passing the fuel element across the weir divider, and may nat
- handle fuel in or out of the core, or in or out of a storage location.
The Senior Operator is in charge of the fuci .iandling evolution and ts responsible for the proper conduct of the evolution.
Rev.10/18/90 - App'd _MM sop /ll-9
-, ,e,.---, .,,,..,r, ,.-n, , , - . - - , ,. , . , . .,,w- ,- w,- -r,, , n.+ ,m-,r- ~w-- .-----,-m-w---m, e v mv , , , . .-.w--
- 11. 4 . 1 Taking a Sample Nonnal water samples taken for water chemistry shall be taken in a 500 ml capped poly bottle. Secondary samples require 1 liter samples. 1 An additional 100 mi sample should be drawn in a urine sample botde for all WT samples and for any secondmy sample that requires radiochemical analysis.
A. Rinse and clean die sample container with D1 water.
H When taking the sample, purge the sample line to rid any stagnant solution.
C Fill the sample container completely. Do not permit the sample to be air mixed while drawing the sample.
D. Cap ti,e container immediately to prevent atmospheric contamination.
E. Note the time, date and source of the sample.
Rev. 10/18/90 App'd h9% SOP /ll-16
SECTION 111 REACTOR CONTROL AND INSTRUMENTATION SYSTEM !
I
!!!.1 Preparation of Reactor Instrumentation for Operation !
111. 1 , 1 General 4
Power to the process lustrtunent panel is provided by the UPS )
st/ stem. Power to the process panel including the neutron monitoring equipment will be misintained continuously. Adjust-ments and calibrations other than outlined in this procedure will be performed by a licensed Reactor Operator or an Electronics Technician. !
After any maintenm es is perfonned on a Nuclear Instrumentation detector or its associa ed 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 Instrument Panel NOTE: " STANDBY" position does not remove detectors from circuit. Electrical transients in this mode may result in damage to detectors or high voltage power supplies.
A. Place all N.I. drawers to zero/zero 1.
R Remove VR units from N.I. drawers.
C. Turn Power Switch to "OFF" on 2 PSI and 2PS2. ,
D. Turn Power Switches for area radiation montfor to "OFF". )
E. Disconnect ARM's bell. )
F. Prop open back-up doors, j l
~ O. Open breakers for sliding doors (504/505). )
H.On Emergency Lighting Panel: 1
- 1. Open E15
- 2. Open E18
- 1. On UPS 2 Panel: )
1, Open breaker #2 )
- 2. Open btcaker #3 1
- 3. Open breaker #5 )
- 4. Open breaker #7 )
- 5. Open breaker M9 ).
- 6. Open breaker #10 )
1 Rev. 10/18/90 App'd W sop /]l].1 3 . r .er ,,s.- -- tr3- - , ,-.,m,+r-_ , , , , ~ --_--~.,,m.k ,ya w.. _ . . . w.g.,..... -r.7, y-we--w,,-.r.,y, . , _ . - , . -.v-,m+.-_-w. m,,y-p~.v -
,r-..p--,es-
J. On UPS 3 Panch )
- 1. . Open breaker #1 l
- 2. Open breaker #2 l
- 3. Open breaker #3 )
- 4. Open breaker #4 l
- 5. Open breaker #5 l 111. 2 Front panel Checkout of Source Range Monitor Channel 1 A Verify that the power to the recorder is on.
11 Set the function switch to " operate".
C. Verify that " drawer inoperauve" 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 "instmment anomaly" llluminates on the annunciator board.
10.-Set functjon switch to "zero". Verify that the "down-scale level" trip indicator is glowing. that Ole LCR meters and )
recorder both indicate 10-1 and that the " period" meters indicate -30 seconds.
F. Set function switch to 105. Verify that the LCR meters and recorder indicate 8 x 104 - 1.5 x 105 and that die "downscale level" trip goes out.
G. Set function switch to 10. Verify diat LCR meters and die recorder indicate 0.8 - 10.2.
H. Set function switch tc " period" position, and " ramp" switch to
" fixed". Verify that " period" meters indicate +3 seconds.
I. Release " ramp" switch, turn " reset" switch to " ramp" position for about two (2) seconds. and set function switch to " operate" position.
J. The SRM is now ready for use. Reset die annunciator.
K. Turn on scal
- r power.
NOTE: The scaler readout mode is to be set at the discredon of the startup operator.
111. 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, a set function switch to " operate".
C. Verify that " drawer inoperadve" (DSIGA) lamp is extinguished.
D. Verify that ' period trip" lamps are extinguished.
Rev.10/18/90 App'd hMTA SOP /lll-2
_ p p;ye m % e am - --
l l' D dlow enough time for the fan motor to coast to a stop and then place the fan motor main breaker forward /revelse 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.
VI.3.3 Winter Operations (Temperatures Expected 13clow 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 an extended 1 period of time and there is a possibility of significant ice build- )
up. perform the following steps to prevent ice buildup in the i 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 automatic valve and float valve.
- 6. Secure air conditioning umt and tag.
- 7. Secure P-4 and tag.
In certain instances, some of these steps may be omitted at the l discretion of the shift supervisor. )
VI.4 Shutdown of the Secondary System Upon completion of shutdown of the reactor, reactor primmy and pool loop cooling systems, the secondary cooling loop can be shutdown as follows:
1 A. Shutdown secondary pump or pumps, if more than one ;
secondary pump is opern",g they should be secured '
simultaneously to minimize check valve slam. This is done from the control room instrument panel.
Rov. 10/18/90 App'd (#hf0 SOP /VI 6
i I
11 Verify that system flow recorder indicates no flow and that the chiller pump, P-4, has automatically started to provide coolant flow to the chiller unit. ]
C Turn off cooling tower fans.
VI.5 Draining and Filling the Secondary System lleat Exchanger and Piping This section has been moved to SMP-21.
VI.G Secondary Water Treatment Procedures l
VI,6.1 Secondary Water System Responsibility l
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 tile total i operation. The secondary water treatment system is designed to ,
minimize corrosion, deposition, microbiological growth, and other major chemical problems which are present in the secondary cooling water system.
VI.6.2 Secondary Water ConductMty Control To control conductivity (total dissolved solids), water is sampled and monitored by the conductMty unit, if the conduc- )
tMty is greater than thesystem set point, an automatic blowdown is initiated. The freshwater makeup,~which replaces the water lost through the blow-down, lowers the conductMty.
- Rev. 10/18/90 App'd W3R SOP /VI 7
i i
VI.G.6 Secondary Silt. Algae and Mud Control !
Silt and mud buildup is controlled by die feeding of a chemical sitt dispersant to die cooling tower basin. The dispersant is added to ensure solids remain suspended a sufficient amount of time to allow Ole secondary blowdown to remove them from die system. This reduces secondary conductivity and minimizes the buildup of silt in low flow areas, a fouling condluon.
Microbiological and algae growth is controlled by the addition of two microblocides/algaecides. The addition frequency is determined by weather condluons and reactor operations.
VI. 7 Secondary System Operation on Maintenance / I Refueling Days f
A Start either Pd. P 2. or P 3 and run as necessary to ) l maintain primary and pool system temperatures.
NOTE: Fans may need to be run also to mc intain proper cold- )
deck temperatures, l r
t 3
e
' Rev,10/18 /90 App'd U$W SOPNI .
< , - -e,-w- ..-.,--.,...-.m ...m...w-o, .a.e.,,,..-,4..y.,r-e,,,,.w-#-, , .,m,-.,+,-w-wr.e-n,,w- .y-,-n-,-y,m
Vll.l.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 temperature conditions have been reached. This check is made by hand calculating the reactor power using the process instmmentation. The results of this calculation !
shall be recorded in the comments section of the Process '
Data log.
Vll.2 Ventilation Exhaust System (EF 13/EF 14) ;
The nonnal exhaust fan line up consists of eitherfan ) -
operating infast speed with the non operatingfan in )
standby (auto). }
To start an exhaustfan, place the controller switch to auto- )
I thefan will start in slow speed. P* ace the controller )
switchfor the non operatingfan to auto place the
)
operatingfan infast speed by pressing the (fast) button on -)-
the controller or at the remote location at the base of the )
ladder. )
Vll.2.1 Fan Failure Alann Normal exhaust fan line up consists of citherfan operating )
infast speed with the non operating fan in standby (auto). }
This condt! ton is indicated by a grcen iight on thefan ) a warning panel in the control room. Any otherfan line up- )
cortfiguration results in the green light being extinguished, l The loss of bothfans, or sign (11cantly degradedflow, actuates )
a pressure switch which operates an audible alarm on thefan -)
warning panel. )
i
?
i j
Rev,_ 10/18/90 App'd }M sopfytt.2 ,
D
-9.-r--s,w.-
.. -.,,,..-y-.,-,oo- -,,w.,re,, ,.q,..%~,m-w,7, ...w.,,-#,e-.,em--y-w.r -**v-emr,+---.-
Vll _ .3 Emergency Power System t
Vll.3.1 Testing of the Emergency Power System
- At least once a week the emergency generator will be started automaucally and permitted to run for at least 30 minutes.
This event will be acted in the console log. A green light ) '
mounted on a side panel in the control room will energize whenever the emergency generator is running. In addition to this, the emergency nerator will be operated for a period of about 30 minutes pi .. to each startup after a shutdown .
exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. On a quarterly basis, cotwnercial power l
- to the auto transfer switch is internipted at unt! substation )
B in order to allow the emergency generator to start and )
imunediately assurne its electrical loads (CP 17). l A modified load test (cpl 7) 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.
Vll.3.2 hianual Start Procedures l hianual starting of the diesel generator under no load I conditions is accomplished as follows: Perform normal l prestart checks (all. fuel, coolant level, etc.). 14ftand )
hold the hfANUAL START switch at the START position, )
and press and hold the CRANK switch. The starter will )
begin cranking and qfter afew 50conds the engine should l start. When the engine starts, release both switches. (( the l l engine does not start qfter 20 to 60 seconds of cranking, l release both switches, waitfor two minutes for the starter ) ,
tnotor to cool and then repeat the statting procedure, if )
the engine does not run after a ~second attempt at starting, -)
refer to the troubleshocting section of the technical manual. l After starting. check the normal operating indications as: -)
RPhi ~ 1800, oil pressure ~ 38 lbs.. Oil temperature ~ 150*, )
and water temperature ~ 180*. The alarm panel wtli l indicate early warning and shutdcwn alarms. )
Rev.10/18/90 e Appd L( g sopfyl13 4
e e-y.. m.,
Vll.3.3 To Stop Engine 1
~
To Stop engine, place the MANUAL START switch to the OFF l position-where it should remain for normal operation.
) l Vll.3.4 Deleted 1
~
Vll.4 Reactor Demineralizer System >
VII,4.1 Normal Operation Normally diere are four mixed resin beds in the system at one time widt two beds on line, one in standby or depleted t and one in die 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 oudet filters. t
' The oudet valve of the system inlet filter is used as a throtding i 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 lG.
Vll.4.~ 1.1 Placing Standby Cleanup Ded on Reactor Service CAUTION must be exercised to prevent a reactor loop low pressure scram from occurring during this procedure!
A. Cl4cck the DI RESIN LOG for the status of the affected bed (s).
B. ItiSURE all valves on STANDBY Di column are CLOSED.
C. OPEN valve DI-2 slighdy 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.
'd
' llev.10/18/90 App'd W sop /y114
- . - . _ . . . - - - - - . _ - - - . . - = . - . . . - - - - - . - - _ . . . . . . - .-
Vll.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 j transfer water.
B. Check the Di resin LOO for the status of the affected bed (s).
C. INSURE that all valves, including unused valves on adjoining systems are CLOSED.
D. INSURE the Dexible hose is connected to the D1 water supply, then OPEN RE 89 and RE 18.
s E. OPEN the RE-25 compressed air isolation valve and set the regulator to the maximum pressure available.
F. PERFORM an 113 water transfer to the DCT if it has not already been done on this bed. (see Vll.4.2.7)
O. OPEN DI-8. DI 9 and DI-13 and allow the bed to drain for four minutes,
- 11. CLOSE DI 9 and DI-13.
- 1. OPEN Dl 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 Dl-7 several times before the hard packed resin breaks loose. When it does. TIIRO'ITLE 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, CLOSE Dl-7 and DI-8.
K. OPEN DI-3, DI 6. RS 3. RS-5 and Dl 13.
L To statt the resin transfer. OPEN R-2 and OBSERVE the bulls-eye for resin movement. Die DI water booster pump may have to be used for adequate Dow. .
M. After the transfer is completed. CLOSE R 2. DI-13. Dl-6, DI-3. RS 3, RS-5 RE-18 and RE 89 (T-300 to Dl-200 isolation valve).
N. CLOSE RE 25, back off on the air regulator and vent the air system, Rev. 10/18/90 App'd WFY\ SOP /Vil- 10
- _ .-. . ~ . . _ - --. . - , . - _ - . -_ - - _ _ -.__-- -
- 0. OPEN RE 68 to vent the pressure in the flexible hose then !
CLOSE RE 68.
P. RECORD the transactJon in both the Di RESIN LOG and the l console log. j Vll.4.2.6 Transfer of Resin from the Storage Tank to R 200 A. Insure that waste tank #2 has the capacuy to accept the )
transfer of water. l B. Check the Di RESIN LOG for the status of the affected bed (s). .i l
C. INSURE all valves. Including unused valves on adjoiningsystems are CLOSED.
D. INSURE the Ocxible 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. OPEN RS-5, RS 1 and Dl 13 and allow the bed to drain for four minutes. .
G. CLOSE RS 5 and DI-13.
H. OPEN RS-4 slowly to achieve the best sounding sparge and 1 allow it to sparge for ten minutes, i L When completed, CLOSE RS-4 and RS-1.
J. OPEN RS-2, RS-7, R 1, RE-7 and RE-16.. 1 K. OPEN R-2 to start the transfer. CDSERVE the resin flow in the bullseye. The DI water booster pump may have to be used to achieve adequate flow.
L When transfer is complete,CLOSE R 2. R-1, RS-2, RS-7, RE-7, RE-16. RE-18 and RE-89 (T-300 to Dl-2OO isolation valve). }
M. CLOSE RL25, back off on the air regulator and vent the :
air system.
i N. OPEN RE-68 to. vent the pressure in the Dexible hose, then CLOSE RE 68.
O. RECORD the transaction in both the Di RESIN LOG and the console log. ,
Rev.10/18/90 App'd W SOP /Vil-l l
- Vil.4.2,7 Transferring Tritiated (311) Water to the DCT A. Check the D1 RESIN !.00 for the status of the affected bed (s).
B. ENSURE all valves, including unused valves on adjoining systems are CLOSED.
C. ENSURE the operability of the DCT system by pumping !
down the collection tank prior to this operation. .
D. ENSURE the flexible hose is connected to the D1 water i supply, then OPEN rib 89 and RE 18. .
E. OPEN RE 25. l I
F, OPEN Dl 9 AND DI-14.
O. OPEN Dl-10 (Dl-200) or Dl ll (DI 201) or Dl 12 (DI 202),
- whichever is applicable to this operation, to start the water transfer. ,
H. When tank is empty, CLOSE DI 10, Dl ll or DI 12 (whichever is applicable) and DI-9.
I. OPEN DI-8, R 2 and DI 3 to fill the tank with water, J, When full, CLOSE Dl 3 and DI-8, K. 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, 1 When completed, CLOSE DI-14. R-2, RE 25, RE 18 and 1 RE 89 (T-300 to DI 200 isolation valve).
' Af. OPEN RE-68 to vent pressure in the flexible hose, then CLOSE RE-68.
- N. RECORD the transactJon in both the Di RESIN LOG and the 3 console log.
- 11. 4 . 3 Providing DI Water to T300 DI water may be sent to T300 with or without the use of the-reverse osmosis unit as a D1300 makeup supply. Due to the fact ;
that DCW, after passing through the R.O. Unit, is much more pure .
than raw DCW, the R.O. Unit is normally utilized to prolong the ]
life of the D1300 resin regeneration. However, there are 1 :
provisions for bypassing the R.O. Unit when sending D1300 )
water directly to D1200 (see VilA.3.3).
Rev.10/18/90 App'd (J#rrA SOP /Vil-12
. ~. - . . . . _ . _ . . . _ _ . _ _ . ~ . _ . . . _ . . _ . . _ - _ _ . , _ _ _ - _ ._ , . _ _ , . _ . - _ _ . . . .
l Vll.7.2 Obtaining a Sample Samples may be obtained as described below. Under nonnal conditions, llealdt physics coverage should not be necessary to draw a sample. liigh activity in the priman' or pool system could, however, present a radiation hazard for this evolutmn.
A chirper is mounted on the hood to indicate a radiation hazard.
A. Turn on hood vent fan and chirper, 11 Check all sample valves closed.
C. Open the appropriate pool or primary sample valve and verify flow by checking the flow indication hubble.
D. After purging for greater than 30 seconds, obtain a 1 ffter 1 sample in a clean poly bott:e from die sample discharge valve.
E. After drawing sample, rinse f.he outside of the bottle with DI water and make appropriate entries in the primary / pool sample sheet.
F Check all sample valves closed, and secure the fume hood fan and chirper.
O. Log the event in the Operations Log 13cok.
Vll.8 Liquid Waste Disposal System VII.8.1 Description A. All drains for potentially contaminated liquids are delivered to the liquid waste retention system (hereafter referred to as the Waste Tanks -WT) in the below grade area of the laboratory portion of the building. The liquid is pumped to the WT from two waste collection sumps provided for collection of potentially radioactive liquids.
Rev. 10/18/90 App'd g g sopfy1120
A. - Sludge Settlement WTl and %T3 are fitted with gravity drains to W'12 through 18" standpipes . This will allow WTl or %T3 to act as settling tanks. When the sludge buildup warrants.
Die sludge is dumped via a 3" drain line at the south end )
of %73 or the north end of WTl into barrels or diying 1 troughs. This sludge is dried and removed as dry active waste.
Il Cuno Filters The waste water will normally be pumped through a waste system filter bank. When the AP is high across them they are replaced with new filters, and the old ones are disposed of as dry active waste. See Section Vll.8.11.
C. Chemical Precipitant Treatment Radioacuve pardculates will attach themselves to carriers which can then be readily filtered out of the %7 water.
- Without these carriers, even die most efficient f;1ters could not remove this radioactive particulate. After filtering, the filters are shipped as dry radioactive waste.
See Section Vll.8.12.
VII 8.3 Dumping Criteria A. The liquid waste is collected and held until an analysis is made to _ determine that die specific activity of all radioactive isotopes in the waste is less than the limit specified in the Code of Federal Regulations. Title 10 Part 20 (10 CFR 20) for dumping liquid waste to the sanitary sewer. In addition to the dumping limit on each isotope.10 CFR 20 also limits the total nethity which die University can dump to the sanitary sewer to 1 curie per year for carbon 14, 5 curies per year for H-3 (tridum) and 1 curie per year for other radioactive material, excluding C-14 and Rev. 10/18/90 App'd (W8M SOP /Vil-22
= _ _ . . . . _ . . ____ . _ _ _ _ _ _ _ _ _ . _ . _ . . _ m
- 2. The RUR is then sent to the Manager of Health Physics (HP) for review. l
- 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 i review is not limited to the above areas. He may recommend l limitations or additional analyses in other areas. If the Manager HP approves of the experiment, he will indicate the addidonal limitauons (if any) recommended 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 condfuons apply the Reactor Manager will submit the RUR to the Reactor Safety Subcommittee (RSSC) for their review. The RSSC conducts the reviews of all new experiments for the Reactor ,
Advisory Committee (RAC). Their review is primarily directed toward . determining if the new experiment - :
introduces an unreviewed safety question in accordance with 10 CFR 50.59. If the RSSC finds that the experiment does not involve an unreviewed safety questions and recommends approval, the RUR review is completed. The RSSC may, 1 however, refer the experiment to the RAC for its review.
This may be done because of unusual hazards, special
. condluons involved or because the RSSC feels that an unreviewed safety question does or may exist. ;
e a
Rev 10/18/90 App'd (M SOP / Vill-2 ,
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. D_Q HQI under any circumstances unlatch the flux trap until the reactor is shut cfown. ]
For verification that the flux trap is properly latched, an operator other than the operator inscrung the flux trap will ,
visually observe its proper latching.
l All flux trap irradlauons will be shown on a flux trap i loading sheet which must be signed by the Reactor Service Engineer or his designated representauve, 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 Specificauon
- 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.
L VIII.2.4 Handling of Irradiated Samples (see H.P. SOP-1 for addiuonal 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.
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 operadon. The Health Physics !
monitor will monitor the operation to minimize radiation exposure to personnel, terrmnaung the operaticn if necessary.
t Rev. 10/18/90- App'd W sop /yl[].7
- _ _ _ _ _ . . _ _ _ . _ ..__.____.,__.___.__.__u___ . _ , . . -
- 1. The authorized p-tube user will inform the control room he is golag to run shielded 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.
3.13oron shielded capsules:
NOTE: The weight limit is only on the boron, i.e.,
the carbon weight in 13C does not count towards the weight limit, a The standard baron shielded capsule with between 10 )
to 15 grams of boron may be run for up tolo seconds in i row 1 or up to 20 seconds in row 2. Verffy with ]
Director of NAA that capsule is the standard baron )
shielded capsule before use. l
- b. Shielded capsules with 10 or less grams of boron may bc )
run for up to 10 seconds in row 1 or 20 seconds in rv.v 2.
G. Except for the boron or cadmium shielded samples, the con-trc'. ling factor foi 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 actkity limits do not further restrict a sample's size, the following weight limits shall apply:
- 1. For irradiation times up to 30 minutes, the maximum weight of irradiated materials in one rabbit will be 2 grams with two exceptions:
a A max 2 mum of 10 grams of water or dried feces;
- b. Only 1 mg of chemical compounds in solution.
- 2. For irradiation times of 30 minutes to I hour, the maximum weight of irradiated materials in one rabbit will be 1 gram with two exceptions:
- a. A maximum of 10 grams of water or dried feces;
- b. Only 500 pg of chemical compounds in soluuon.
Rev. Inn o /on App'd %% SOP /Vlll-12
Vill.4 Beamport Experiments Vill.4.1 Ge 1eral Requirements As with all other experiments, beamport irradiations and measurements must be authorized by an approved RUR.
A. There are four major hazards involved with heamport experiments. They are: 1
- 1. Changes in reactor reactivity due to beamport acthities such as draining or flooding a beamport.
- 2. Exposure of personnel to radiation as a result of movements 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 beamport.
Il The limitations listed below are established to minimize or climinate these hazards.
- 1. The NRC Regulations Tide 10 Part 50 Section 50.540) I require that " Apparatus and mechanisms other than controls. the operation of which may affect the reactMty or power level of a reactor shall be manipulated only widi 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 beamport. 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 operation. These activated gases present a radiation hazard to personnel in containment 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. 10/18/90 App'd h?l% sopfy111 19 l
l SOP Vill.8 RESPONSE PROCEDURES FOR THE ALPHA 1ABORATORY The following procedures shall be used when responding to ,
alarms from the Alpha Laboratory and the Alpha Laboratory !
Argon glove box.
NOTE: Maintaining an inert Argon atmosphere is the principal fire safety feature of the Argon glove box. ;
The following alanus may not have immediate safety '
implications. however, they indicate a degradation in the fire safety feature of the Argon glove box and indicate a potendal loss of glove box integrity.
SOP Vill.8.1- RESPONSE TO ALPHA LABORATORY HIGH AIRBOIWE RADIOACTIVI'lY AIARM (Exhaust and/or Room Monitor) 1.- Noufy shift supervisor and Health Physics Manager. ;
- 2. Monitor readings on facility exhaust partleulate monitor in i control room. An assessment of the offsite radiological consequences shall be determined.
- 3. If the stack paruculate monitor indicates a steady increase coinciding with an ALPHA 6 alarm, secure the reactor and EF-13 and EF-14 at the breaker on the Emergency 1 Distribudon Center.
- 4. Ensure persons have evacuated the Alpha Laboratory, if no
- experimenter is present, call the on call experimenter as soon as time permits.
WARNING: - (Do NOT enter room except for life saving or -
- ' accident mitigatjon efforts unut Health Physics arrives.)
- 5. Secure the Alpha Laboratory exhaust and supply fans locally.
- 6. Shut the Alpha Laboratory supply damper only.
- 7. .With Health Physics coverage, enter Alpha Laboratory using respirators to locate and repair source of airborne acdvity.
SUBSEQUENT ACTION: Assist recovery and decontaminauon procedures or the Alpha Laboratory and basement in vicinity of Alpha Laboratory.
New 10/18/90 App'd MY\ SOP / Vill-43 =
y
,e- - _
u'm- -w',..,
--e . er y , ., - m w, w n--- - - p f -,no w- se ' v w w -y= w
- rv v m se-e w "m r'" . 'v eaa- ve F -O rg- - cv v* 'vwi v e r y C '-
SOP Vill.8.2 lilGli OXYGEN IN G1,OVE llOX Al. ARM NOTE: The continuously operated oxygen monitor (located in the DRI-TRAIN racid is the most sensitive indication of air leakage into the Argon glove box.
- 1. Verify no incteased altborne activity on the St.ick monitor.
- 2. Contact TRUMP-S scientist on call. Contact llealth Physics technielan.
- 3. Before entering laboratory, check the Argon glove box pressure indicated on the Photobelle gauge located on top of the Argon glove box.
a) If it is in the normal range (- 0.2 to - 1.0 inches of water) then there is no serious leak in the glove box.
b) If pressure is near zero, then die possibility of a leak exists and the glove box should be visually inspected from the window to the Alpha laboratory.
- 4. Check the Alpha laboratory exhaust monitor and the Alpha laboratory room monitor for indication of elevated activity.
a) If no elevated activity is indleated on either monitor, enter the laboratory by normal entry procedure.
TAM - 10.
b) If elevated activity is indicated, see SOP Vill.8.1 Response to Alpha Laboratory liigh Altborne.
- 5. Check NITRAIN/DRI TRAIN units for loss of power.
G. Check glove ports covered.
- 8. Investigate source of leakage and temporarily seal, if possible. ..
- 9. Exit Alpha las i tory by normal exit procedures, TAM-10.
- 10. Assist TRUMPQ 4clentjst and llealth Physics in determining so , ce and corrective action.
New 10/18/90 App'd 3WM SOP / Vill 44
i SOP Vill.8.3 LOW ARGON SYSTEM PRESSURE AIARM NOTE: This alarm may indicate an Argon system leak or a loss ofintegrity of the Argon glove box. (A loss of glove box ;
integrity should also cause High Oxygen Alarm). The !
pressurtzed Argon gas bottles provide Argon makeup to the Argon conditioning system (a recirculating purification system) associated with the Argon glove ,
box.
- 1. Call the TRUMP S scientist on call Contact Health Physics technician. ;
- 2. Check the Argon bank pressure at inner passageway.
Replace bottles, if necessary. .
laboratory for leaks. Repair any leaks, if possible.
- 4. Before entering the laboratory, check the Argon glove box pressure indicated on the Photohelic gauge located on top of the Argon glove box, a) If it is the normal range ( 0.2 to 1.0 inches of water) dien there is no serious leak in the glove box, b) If pressure is near zero, then the possibility of a le .k exists and the glove box should be visually inspected from the Alpha laboratory window.
- 5. Check the Alpha laboratory exhaust monitor and the Alpha laboratory room monitor for indication of elevated activity, a) If no elevated activity is indicated on either monitor, enter the laboratory by normal entering procedure, TAM- 10.
b) lf activity is indicated, see SOP Vill.3.1, Response to
. Alpha Laboratory High Airborne Activity.
- 6. Check NITRAIN/DRI'ITMIN t.ntts for loss of electrical power (pressure control system is part of DRI-TRAIN unit).
- 8. If Argon pressure cannot be restored in 90 minutes or if ;
oxygen monitor alarms and indicates greater than 100 ppm. Secure the Argon box well heater.
- 9. Exit Alpha laboratory by nonnal exit procedure. TAM-10.
- 10. Assist TRUMP S scientist and Health Physics in determining corrective actions.
New 10/18/90 App'd MdW\ SOP /Vlil-45
.. . _ _ . _ . . ... _ _.__ . _ ~ .._ ... _ . _ _.._., ~. _ ._._ _ _
l l
THIS PAGE INTENTIONALLY LElT 131ANK I
P New 10/18/90 App'd Wah . SOP / Vill 4G
REACTOR STARTUP CllECKSHEET DATE:
FULL POWER OPERGON TIME LStarted):
BUILDING AND MECllANICAL EQU1PMEhT CllECKLIST I i 1. Emergency air cornpressor lload test for 30 minutes after maintenance day).
- 2. Beamport Floor; a Deampon radiation shiciding (as required).
- b. Deamport status checked / updated. }
- c. Seal trench low level alann tested (after matntenance day).
- d. Check closed beamport floor access gates.
)
- 3. a. Check operation of fan failure buner and warning light. Notify Alpha lab of momentary ]
ventilation loss. (Reg'd if shutdown longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ) )
. b. Test stack monitor and low flow alann per SOP while in west tower.
- c. Test UPS alarm panel. ]
- 4. Emergency generator availability checked as per Sect !.A and 111. of D.C. checklist. 1 (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 emergency generator for 30 nunutes ) '
l I 5. Emergency pool fill. (Check valves PN 1 and PlV 2 locked open.)
- 6. Visual check of CT and secondary equipment:
- a. Oil level in CT fans nomial (after maintenance day).
-b-. Secondary makeup isolation valve power switch closed, valve cycled to verify operauon and placed in auto mode.
- 7. Visual check of room 114 equipment:
- a. P501A and PS01D coolant water valves open
- b. Pump controllers unlocked to stan (as required).
- c. Check valves 599A and 599D open.
- d. Air valve for valve operating header (VOP31) open.
- e. Nitrogen back up valve open.
]
- f. Atr/ Nitrogen cross connect valve open.
l
- g. S1 and S2 hydnulic pumps on (011 level nonnal)
- h. Valves 51 and S2 cycled in manual mode and positioned as required
- 1. Vent the pool hold up tank.
J. Vent the pool skimmer system pump.
- k. Check the pipe trench free of water Check the four pipe annulus drain valves for water leaksge after maintenance days.
- 1. Add D1 water to beamport and pool overflow loop seals.
- m. Check oil reservoir for puups 501A. 501B. and 533 for adequate supply. Add if necessary.
- n. Visually check rcom i14 and D1 are' after all systems are in operation.
- 8. Reactor Pool;
- a. Reflector expenmentalloadings venfacd and secured for start up.
- b. Flux trap expenmentalloading venfted and secured for start up, or strainer in place.
- c. Check power on and reset, as necessary, silicon integrator, totahzer setung sibcon rotator an alarni system.
Rev.10/18/90 App'd . SOP /A la
l REACTOR STARTUP CliECKSliELT FULL POWER OPERATION (cont'd) ;
Page 2 1
REACTOR CONTROL SYSTEM C1'ECRI.!ST I 1. All chan dnves 01; charts timed and dated, IRM recorder to slow.
- 2. Fan failure warning system cleared.
- 3. Annunciator board energtzed: horn OIL
- 4. Television receiver on.
- 5. Primary / pool drain collection system in senice per SOP. (Manually pump DCT G. Secondary system on hne per SOP (as needed).
- 7. Primary system on line per SOP:
l a. Pnmary cleanup system on line.
- 8. Pool system on hne per SOP:
- a. Pool cleanup system on Itne.
- b. Pool reflector AP inps set as required.
- 9. Nuclear Instmmentation check completed per SOP:
l I a. The followmg tnp values were obtained dunng the check:
IRM 2 run in _ seconds (11 1 1) Scram seconds (9 1 1) 1RM 3 nm in seconds (11 1) Scram seconds ID : 1)
WRM 47uu in % (114 : 1) Scram % (119 : ))
PRM.5 run in % (114 1) ' cram
. % (119 1 1)
PRM.0 mn in % (114 : 11 Scram % (119 1)
_. 10. Chanrie! 4,5, and 6 pots returned tc last heat balance position.
I1. SDM-1 detector response checked and set to indicate > 1 eps.
- 12. Check of process radiation monitors (front panel s.becksi:
- a. Fission product monitor,
- b. Secondary coolant monitor.
NOTE: ltems 13 through 34 are to be completed in sequence inunedtately pnor to pulling rods for a reactor stanup.
- 13. Annunciator tested.
- 14. Annunciator alann cleared or noted.
- 15. Power selector switch 1S8 in position required.
- 16. a. Bypass sw1tches 2540 and 2S41 in position required.
- b. All keys removed from bypass switches.
- 17. Master switch ISI in "On* position.
- 18. Magnet current switch on check tReactor On* lights.
- 19. Reactor isolation, facility evacuation and ARMS checks la'ter maintenance day) These items .
are to be checked w1th scrams and rod run ins reset, and when appropnate items are actuated. verify that the TAA's do tnp.
l l a. Reactor isolation inpfrom security cabinet.(Not(fy police on security alarm.) )
(leave valves and doors closed) (after maint. day)
- b. Reactor Isolanon switch. l
- c. Facility evacuat. ton switch (check outer contatnment homs) (after maint, day).
. Rev.10/81/90 App'd M SOP /A lb
REACTOR STARTUP CHECKSilF13 FULL POWER OPERATION (cont'd)
Pace 3
[ }
- d. AfotS trip setpotnts checked and inpped, check buner operational kcally for all channels and remotely for channels 1 through 4 and 9.
Channel 1 Deara Room South Wall Channel 2 Deam Room West Wall Channel 3 Deam Room North Wall Channel 4 - Fuel Storage Vault Channel G Cooling Equipment Room 114 Channel 7 Dutiding Cxhaust Air plenum (after maintenance day).
Channel 8 Reactor Drtdge (sw1tch in *Nonnal*1 (after maintenance day)
Channel 9 Reactor Drtdge backup (switch in
- upscale *) (aher maint. day)
- e. Check HV readtngs: volts (520 3.10 VDC)
- f. Check 150V reading: volts (150 VDC 420)
( -
5)
- g. Trip backup monitor with attached source tafter maintenance day).
- h. Reactor it.olation homs switch in *lsolation Hotm On* position. Vah es and doors open
- 1. All ARMS tnps set per SOP, 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 nan in function at 10% withdrawn and annunctator at rod bottomed
- 21. Raise blade A to 2* and manually scram.
- 22. Raise blade D to 2" and inp manual rod run in.
- 23. Raise blade C to 2* and scram by WRM trip.
- 25. Annunctator board energued; born on.
- 26. Jumper and tag log cleared or updated.
- 27. IRM recorder in fast speed.
- 28. Check magnet curTent for 90 ma on each magnet.
- 29. Cycle WRM range switch.
- 30. Reset
- white rat
- scram monitor.
- 31. Esumated critical blade position (corrected): inches.
- 32. Pre startup prrcess data taken.
- 33. Routine patrol completed.
- 34. All reactor and heense related systems upon which maintenance was perfonned have been reviewed and are operable.
{ j 35. Reactor ready for startup.
Time (Completed)
Shift Supenhor/ Lead Senior Operator Rev.10/18/40 App'd OMD1 SOP / Ale ]
.=. - . .. .
71{l5 PACE !?ilE!il10NALLY LEFT 14 TANK
=
New.Q16/90 App'd M4k SOP /A-id
._= . -- . . . _ _ . . .
REACTOR ROUTINE PATROL DATE:_
1 Time of start oi patrot
- 2. Time and cate all charts 3, Check ARIAS trip settings b
- 4. Visuai check of entire pool 5, Anti siphon tank pretsure 36 psig 23 psi 6< Nor1h iso door seat pressure 18 28 psig
- 7. South iso coor seal pressure 18 23 psig
- 8. 5th level backup doors o;xn
- 9. 5th levet detector reading 0-3 5 mr/h*
- 10. 5th level trip' point set 3.5 mr/hr 11.16' iso viv A air prtissure 45 55 psig
- 12. W !so /tv B air pressure >90 psig
- 13. Emerg air compress on standby e n,
[(rfoseav 14, Containment hobmp pumps Operable 15, DCW pressure 50 65 psig I
- 16. Door 101 seal pressure 18 28 psig 17, GP tloor Conditions normal
- 18. Fuel vaalt meo 19, inner airtock coor seal pressure 18 28 psig
- 20. Outer airlock door seal pressure 18-28 psig d
- 21. Cold deck temperature 45 65 deg F I
- 22. T400 level >2000 gal
- 23. T 301 level <6000 gal
- 24. Argon bank pressure >200 psis 1
On the first routino patrol of the day or the first patrol after a startup, drain all water from the anti-siphon system, If draining causes the pressure to drop signifi-cantly, retuin to the middle of the band (36 psig) and record the pressure here. If a corsdition or reading is normal, enter a "U (for conditions) or the reading in the applicable box. If the condition is abnormal, enter the condition or reading and circle it. Explain all abnormal conditions or readings in the REMARKS on page 3.
Rev.10/18Q0 App'd Wow SOP /A-8a
REACTOR ROUTINE PATROL
~ DATE:
- 85. Labyrinth sump - Level < Alarm Pt.
- 26. RO_ unit power _' ON
- 27. AO unit temperature 2 4' 2 8 *C or Standby -!
28.- RO unit pressure 190 200 psig or siby '
room NO Alarms Indicated L
[
Thermostat >55 T ,
Temp > 40*F '
- 30. T 300, T 301. Room Thermostat>40e >55{
Temp.
- 31. Rm 114 particulate filter AP <2.5* water 32a. EG. Rm. (Perform complete Thermostat >60 F (checklist on Sunday) Temp. >50%
32b. Battery charging current <1 amp 32c. Battery Voltage > 28 V
- 33. External doors - Alllocked except east when sec on duty
' .id. CT basin water level 5 10*
- 35. Automatic secondary makeup viv Auto or open 36.' Acid day tank level Visible
- 37. Acid control and pH ; Range as posted
- 38. Blowdown control /cond, ,
Range as posted
- 40. P pump (s) running
- 47. Pump strainer AP 0 7.0 psi
- 42. Dischargo pressure
- 43. Pump strainer AP .
O _- 7.0 psl = .
- 44. Discharge pressure
- 46. WT booster fan Running 47." Fission product monitor flow 95 105 cc/ min
- 48. Viv control header pressure-90 120 psig
- 49. Pressurizer N2 supply press 90 100 psig NOTE: - Numbers . rearranged only.
Rev.10/18/90 App'd Wem SOP /A-8b
REACTOR ROUTINE PATROL DATE:
- 50. Check rm.114 from door 51 Dettech oil filter
- red level-and blow down < 75% dark red
- 52. Seal trench 61 66*
Run pump on days
- 53. Bank on service A or B
- 54. Full N2 bottles Total > 3
- 55. Bank B bottle pressure > 250 psig
- 56. Bank A bottle pressure > 250 psig '
- 57. N2 header pressure 135 145 psi
- 58. Waste tank #3 level
- 59. Waste tank #2 level
- 60. Waste tank #1 level
- 61. Doors to Gl. WTs, Domin, ~~
Am 114. and Ct Tunnel
- 62. Time of completion of patrol
- 63. Operator initials REMARKS:
NOTE: Numbers rearranged only.
Rev 10/18/90 App'd IA$1(\
SOP /A-8c
R8mJRN ORFAAL TO HEETH PHYS?CS OFFCE No. __
WASTE TANK SAMPLE REPORT TANK NO. TANK LEVEL __ (Liters)
]
SAMPLER . _ . _ .
Tl M E _._ DATE
- 1. Analysis Results Nuctide Half Ufe - EhssicM Form C.Qncentration liPC Activity
_A H3 12 3Y U-pH FRACTON OF MPC Analysis by TIME DATE Concentration fuCitml) Total Volume (liters) Activity (mCO (a)
(b) 2, Approvals Required for:
Any Discharge . ., , ,,, , , ,, , , , , , , , ,,
Shift Supervisor Disenarge of > 10 mci of H3, > 2 mei of otner activity, or to Secondary System .
Discharge Limit Approved . ., , ,
- 3. Action Taken Date Discharged Time Discharged Volume Discharged (Liters)
Tantt Discnarged to (check one) Sanitary Sewer Secondary System Not Discharged REMARKS Rev.- 10/18/90 App'd M% SOP /A Ila
MURR TAG OUT SHEET TAG SHEET #
TYPE OF TAG RED / YELLOW (CIRCLE ONE)
SYSTEM OR COMPONENT REASON FOR TAG OUT SHIFT SUPERVISOR APPROVAL SHIFT SUPERVISOR REVIEW FACILITY MANAGER OPERATIONS ENGINEER TAG REMOVAL AND REPOSITIONING APPROVAL TAGGED DATE EQUlPMENT ---3g --
- gy- - --
I INI TIA1.S gg g New 10/18/90 App'd (A M SOP /A-20a
TAGGD DATE l TAG POSRON TAGED INITIALS tUA3ER EOUlPMENT - ---------- ------- ---------
LitTAGGED DATE INITIALS POSITON QINED l
New 10/18/90 App'd W3" SOP!A-20b
MURR TAG OUT INDEX RECORD TAG SHEET NUMBER MTE T$
MC MA OR WAPCNENT DATE CLEARED ESTABUSHED (TRANSFER TO REDI TAG OUT SHEET) NB1CW R/Y R/Y R/Y R/Y R/Y R/Y l R/Y R/Y R/Y
=
R/Y R/Y R/Y R/Y R/Y R/Y
, R/Y
. R/Y R/Y R/Y ._
R/Y R/Y R/Y New 10/18/90 App'd V* SOP /A-20c
MURR TAG OUT INDEX RECORD TAG SHEET CATE TC) SYSTBAOR CCMPCNEM DATE CLEARED NUMBER ESTABLISHED ME (TRANSFER TO RED /
TAG OUT SHEET) YELLON R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y R/Y New 10/18/90 App'd tNOh SOP /A-20d
_ _ __ . ~ . . _ . .
=_._ - - - . _ . . _ . _ _ _ _ - - . _ - . .- __ ..
STANDARD OPERATING PROCEDURES 2nd Edition, Effective Date: 5/02/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.)
Revision Number 4 Revision Date: April 30.1990 SOP /Ill-8 SOP /lil-9 ~
SOP /Ill-10 SOP /Ill-11 SOP /Ill-12 SOP /Vl-1 SOP /VI-6 SOP /Vil-2 SOP /VII-20 SOP /Vil-31 ,
SOP / Vill 13 SOP /A-lb SOP /A-l c -
SOP /A-5b SOP /A-Sc SOP /A-8a SOP /A-8b SOP /A-8c 11- 3
E. Increase power to original level.
F. leg final new pot setting, 111.7 Check of Process Radiauon Monitors 111.7.1 Operational Check of Seconday Coolant and Mssion Product /
Monitors respectively. J A Lower alarm setpoint until annunciator alarms. ]
8 Place letel set switch up and ac{ lust alarm setting to )
10k cpm 10%. J C Lower alann setpoint until anunciator alarms. J
'D. Place level set switch up to and adjust alarm setting to l 12k cpm 10%. ]
'111. 7 .2 Operauonal 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 received.
Also verify that the local meter reads within 10% of the test
.. reading marked on the meter face.
D. Return the iodine mode switch to the "N" posidon.
E. Press the " reset" tactton until the lodine meter and recorder readings return to normal. do not drive them to the duvnscale position. Reset the annunciator.
F. Place the mode switch for the particulate / gas monitor in the "T" position.
Rev. A no / m App'd \AAM SOP /Ill-8
111. 8 Area Radiation Monitoring System The area radiation monitoring system will be in operation conunuously 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 stauon trip points shall be set as follows:
Station I BP North Wall 2 X acceptable background )
Station 2 BP West Wall 2 X acceptable background ]
Station 3 BP South Wall . 2 X acceptable background ]
Station 4- Exhaust Plenum 1mr/hr or 10 X normal ]
operating background ]
Station 6 Bridge AIARA 3OOmr/hr alert }
10K mr/hr alarm / trip ]
Station 7 Bridge 50 mr/hr or 10 X normal ]
operating background ]
Station 8 Nuclepare 2 X normal operating ]
background ]
Station 9 - Fuel Vault 2 X normal operating ]
background i Station 10 Room 114 2 X normal operating ]
background ]
Station 11 Exhaust Plenum #2 1 mr/hr or 10 X normal I operating background i At least once a month the system will be checked according to the ]
following procedure: }
NOTE: GREEN Lamp serves as Normal light and Check Source )
actuating switch (push to actuate source). , )
AMBER Lamp serves as Alert alarm (push to reset). ]
RED Lamp serves as High alarm (push to reseth The i alert has been set up on all ARMS units except for i :
both bridges. ]
i A. At station 1. operate the check source pushbutton and venfy ]
that when trip point is reached, the RED alarm lamp lights at i the Electronic Channel, and the RED alarm lamp lights and the ]
AUDIBLE alarm sounds at the Remote Alarm Unit. l B. Repeat step A for Stations 2. 3. 8, 9 and 10. I Rev. 4 / 30/ 91 ' App'd M SOP /lli-9
C The source check for Stations 4, 6, 7 and 11 while performing ]
the above-menttoned functtons, also inittates a reactor scram )
.and Containment building isolation. ]
NOTE' For normal startup checks, testing of the manually ]
initiated reactor isolation and faculty evacuation trips ]
wul be performed in conjunction with the above ]
checks with the horns suenced and the isolation ]
valves and doors closed. ]
D. To conduct source checks of Stations 4, 6, 7 and 11: }
NOTE: For Station 6 (Bridge AIARA) and 7 (bridge), the ]
alarm setpoints wul have to be lowered to test ]
operation, as the check source wul not provide ]
enough defection to actuate alarm. ]
- 1. . Reset scram and rod run in trip actuators. ]
- 2. Notify all persons within thefaculty of intentions to ]
perform the check. ]
- 3. Operate check source push button, except Stations 6 & 7 ]
and monitor point of trip. verifying thefollowing has ]
occurred: )
a Scram and rod run in trip actuator ampl{flers ]
tripped. ]
- b. Building Air Plenum and Bridge High Activity scram ]
alarm indicated on annunciator. ]
- c. Isolation scram alarm indicated on annunciator. ]
- d. 16" isolation valves indicate closed. ]
- e. Backup doors closed. ]
f Containment isolation hams have sounded. ]
- g. Isolation doars MO-504 and MO-505 indicate closed. ]
- h. Red. flasher light outside outer containment door is ]
fashing. ]
- 4. 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. Nuclepore ]
valve cutout switch and backup doors cut out switch ]
may be turned to the off position, leaving the valves l and doors closed. ]
- c. The motor operated isolation doors may be left in the ]
closed position. ]
Rev. 4 / 30 / 91 App'd bWM SOP /III-10
- 5. When the checks have been perfonned as required, reset J the tripped Station 4, 6, 7 or 11. ]
NOTE: Reset alarm setpointsfor stations 6 and 7. ]
- 6. Close the 16" isolation valve cutout switch. verifij the ]
valves indicate open, return the Nuclepare and back up ]
doors cutout switches to normal. ]
- 7. Open isolation doors MO-504 and MO-505 by depressing )
the open pushbutton until the doors are completely open )
and bothfans have started j
- 8. Perform a visual inspection of the ventilation system on. ]
the J1fth level. ]
- 9. Insure isolation horn cutout switch turned on. }
- 10. Not{fy all persons within thefacility that checks are ]
completed and that they should regard allfurther alarms. ]
Rev. 4 / 3n / al App'd hvh SOP /Ill- 11
.. . .- . _. - .~ .- . ~. .. .- .. . . - .
i k
i NOTE: 'IMIS PAGE INTENTIONALLY LEFT BLWK b
Rev. 4/30/91 App'd LWf" SOP /III-12 l
- .~ .
SECTION VI SECONDARY COOLING SYSTEM VI.1 Startup 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.
- 3. Oil level in the gear reducers to the fans is normal.
- 4. The automade sump makeup water isolation valve electrical power switch is in auto.
R The following manually operated valves in the cooling tower should be in positions indicated:
Open ' Closed S-17 S-9 S-105 S-129
-S-18 S-10 S-106 S-101 S S-11 S-107 S-126 S-20 S-12 -S-108 S-121 S-21 S-Il8 S-109 S-123 S-22 S-119 S-110 S-125
'S-155 S-120 S-111 S-127 S-5 S-ll7 S-ll2 S-Il3 S-6 S-114 S-163 S-102 S-7 S-115 S-128 S-4 7B /
S-8. S-116 . S-4 7A /
NOTE: S-47A provides cooling to chiller units. J C. The following valves in equipment room 114 passageway and waste tank room should be in the postuons indicated:
Onen Closed S-152 S-151 S-103 'S-169 S-153 S-150 S-160 S-104 S-159 S-170 Rev. 4/30/91 App'd 1Avfn SOP /Vl- 1 T
-
- w ,,w ,,u,a, + - - - , - -v-. g
D. Allow enough time for the fan motor to coast to a stop and then place the fan motor main breaker forward / reverse switch to reverse.
E. Notify the control room to start the fan (Fast speed is ]
recommended). It will now be rtmning in reverse to force heat 1 out through the ice covered fouocrs orJill. J F. Periodically check to see ifice is clear.
G. Reversefan operation should not exceed 20 minutes, if any )
ice build up is noticed on thefan blades or cylinder. ]
H. When the ice has cleared. follow steps C & D above to return ]
thefan to theforward directionfor operation as necessary. ]
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 plasuc 1111.
When the cooling tower is to be left unattended for an extended period of time and there is a possibility of significant ice build-up. - 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 automatic valve and float valve.
- 6. Secure ajr conditioning unit and tag.
- 7. ~ Secure P-4 and tag.
In certain instances, some of these steps may be omitted at the discretion of the shift supervisor.
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 shutdown as follows:
A. Shutdown secondary pump or pumps. If more than one '
secondary pump is operatmg. they should be secured simultaneously to minimize check valve slam. This is done from the control room instrument panel.
Rev. 4/30/92 App'd tA21Y\ SOP /VI-6
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 temperature conditions have been rear ned. This check is made by hand calculating the reactor power using the process instrumentauon.
The results of this calculation shall be recorded in the comments section of the Process Data log.
Vll 2 Ventilation Exhaust System (EF-13/EF-14)
The normal exhaust fan line-up consists of either fan operating in fast speed with the non-operating fan in standby (auto).
NOTE: Prior to operation infast speed. venfy SF-1. SF-2, J RF-2, RTAH-1 and RTAH-2 are in operation and )
Alpha Lab. supply and exhaustfans are both in AUTD ]
and running. ]
I To start an exhaust fan, place the controller switch to auto-the fan will start in slow speed, Place the controller switch for the non-operating fan to auto. Place the operating fan in fast speed by pressing the (fast) button on the controller or at the remote location at the base of the ladder.
VII.2.1 Fan Failure Alarm Normal exhaust fan line-up consists of either fan operaung in fast speed with the non-operating fan in standby (auto).
This condidon is indicated by a green light on the fan warning panel in the control room. Any other fan line-up configurauon results in the green light being extinguished.
The loss of both fans, or significantly degraded flow, actuates a pressure switch which operates an audible alarm on the fan warning panel.
Rev. 4/30/9 App'd lbWt SOP /VII-2
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l Vll.7.2 - Obtaining a Sample Samples may be obtained as described below. Under normal condluons. Health Physics coverage should not be necessary to draw a sample. High activity in the primary or pool system could, however, present a radiation hazard for this evolution.
A chirper is mounted on the hood to indicate a radiation hazard.
A Turn on hood vent fan and chirper.
a Check all sample valves closed. .
C. Open the appropriate pool or primary sample valve and verify flow by checking the flow indicauon bubble.
D. After purging for greater than 30 seconds. obtain a 500 mi sample in a clean poly bottle from the sample discharge valve.
When the poly bottle is full. shut the pnmanJ/ pool isolation ]
e valvefirst to ver{fy no leakage through the sample valve ]
manifold. ]
L' E. Shut the sample discharge valve, rinse the outside of the bottic ]
with DI water and make appropriate entries in the primary / pool sample sheet.
F. Check all sample valves closed, and secure the fume hood fan and chirper.
G. Log the event in the Operations Log Book.
Vll.8 Liquid Waste Disposal System VII.8.1 - Description -
- A All drains for potendally contaminated 11gulds are delivered to the liquid waste retenuon system (hereafter referred to as the Waste Tanks -WO in the below grade area of the laboratory pordon of the building. The liquid is pumped to the WT from two waste collection sumps provided for collecuon of potentially radioacuve liquids.
Rev. 4/30/91 App'd k SOP /VII-20
Vll.9.3 System OperatJon i
The operation of the air and N2 systems is fully automatic.
The operation of the system is monitored every four hours during plant operatjon. The only manual evolutions required are 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 itr. volume has turned dark red in color.
Vil 9.4 System Shutdown After the reactor has been secured and no further valve operations are anticipated, the air and N2 systems are shut down as follows:
A. Close the N2 to air cross-connect valve VOP8 to reduce N2 consumption.
B. Close the N2 cut out valve VOP15 in room 114.
C. Close air cut out valve VOP31 in room 114.
D. Open header bleed valve VOP37, bleed to atmospheric 1 pressure, leavtng valve open.
E. Secure the N2 control system by opening the electrical switch at the bottle station.
Vll.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. 4 /30 '91 App'd id SOP /VII-31 l,
( The weight limite above do not include the weight of the rabbit.
polyethylene vial, or packing, or the cadmium (or other metal) shields.
The maximum irradiation time for most samples will be one hour at power levels <5 MW and 30 minutes for power levels
> 5 MW. Hair, fibers, paint, air filters and flux monitors may be irradiated for a nmximum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at power levels < 5 MW and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at power levels >5 MW. The following additional limitations shall apply for irradiauons >10 minutes:
- 1. Primary encapsulation will be heat-scaled high-density polyethylene vials (llolland vials).
- 2. Liquid samples may be irradiated for up to 30 minutes provided pin holes are punched in the top of the polythylene vial to relieve pressure.
Deviations from the above weight and time limitations must be specifically authorized in the experimenter's RUR.
Vill.3.3 Rabbit Limitauons 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 irradladons (see Section Vill.3.2.B). Each high density rabbit will be limited to six insertions not to exceed a 1 total irradiation time of one hour or a single insertion not to ]
exceed a total irradiation time of two hours. To account for the ]
trradiauon history of high density rabbits, the experirnenter will place one mark with a marking pen on the high density rabbit for each insertion up to and including 10 minutes. For irradtauons longer than 10 minutes, a mark will be placed on the rabbit for each 10 minute period or fracuan there of. For example, if a rabblus 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. coo /m App'd Ak#k SOP /Vlli-13
-. . -- ._- .. ~ - . ..
f.
REACTOR STARTUP CHECKSHEET FULL POWER OPERATION (cont'd)
Page 2 REACTOR CON'ITIOL SYSEM CHECKLIST
- 1. All chart dnves on: charts timed and dated. IRM recorder to slow.
- 2. - Fan failure warning system clearedi
- 3. Annunciator board energtzed; horn off.
- 4. Television receiver on.
_ 5. Prunary/ pool drain collection system in service per SOP (Manually pump DCT)
- 6. Secondary system on line per SOP (as needed).
- 7. Primary system on Itne per SOP:
l } a, Primary cleanup system on line.
S. Pool system on hne per SOP:
- a. Pool cleanup system on line,
- b. Pool reflector aP (nps set as required.
- 9. Nuclear Instrumentation check completed per SOP:
LJ a. The fotiowing inn vaiues were obtained during the check:
IRM 2 run-in seconds (11 : 1) Scram seconds (9 1).
IRM-3 run-in seconds (l1 : 1) Scram seconds '9 : 1)
WRM F " in -
% (114 1) Scram % (119 : 1)
PRM b .an us % (114 : 1) Scram % (119 : 1)
PRM-6 run-in % (114 1) Scram % (119 : 1)
- 10. Channel 4. 5, and 6 pots returned to last heat balance position.
I1. SRM 1 detector response checked and set to indicate > 1 cps.
- 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 immedtately pnor to pulling rods for a reactor startup,
- 13. Annunciator tested.
14f Annunciator alamt cleared or noted.
- 15. Power selector sw1tch .158 in position required.
- 16. a. Bypass switches 2S40 and 2S41 in position required,
- b. All keys removed from bypass switches.
- 17. Master switch 1S1 in "On' position.
- 18. ' Magnet current switch on, check " Reactor On" !!ghts.
- 19. Reactor isolauon facility evacuauon and ARMS checks f fter maintenance day) These items are to be checked with scrams and rod run ins reset, and when appropnate items are actuated. venfy that the TAA's do inp. (announce test tofacGity and nottfy pohce of secunty.- l alarm) 1 i } a. Reactor isolation tnp from secunty cabinet.
Ileave valves and doors closed) (after maint. day) i b. Reactor Isolauon switch.
j c. Facility evacuauon switch (check outer containment homs) tafter mamt. dayj,
}
l Rev. 4/30/91- App'd M SOP /A-lb l
- REACTOR STARTUP CHECKSHElFT FULL POWER OPERATION teont'd)
' Pace 3 I' I d. ARMS tnp setpoints checked and tripped, check bur 2er operational remotely for all 1-channels (SOP 111.8); I
-Channel 1 Beam Room North Wall }
Channel 2 - Beam Rcom West n'all I Channel 3 - Beam Room South Wall I Channel 4 - Exhaust Plenum i Channel 6 Bndge ALARA J Channel 7 Reactor Dndge ]
Channel 8 Nuclepare ]
Channel 9 Fuel Vault )
Channel 10 Cooling Equipment Room 114 ]
Channel il Exhaust Plenum 22[D/U) ]
- e. Reactor Isolation horns swuch in " Isolation Horns On* position. V .s and doors open.
- f. All ARMS tnps set per SOP.
- g. Check ventuation fans, containm6nt and backup doors.
- h. Announce completion of test lofacaity evacuation isolation systemlNonfy policei j
' 20. Opente reg blade from full-out to full in and set at 10" + .05"
- a. . Check rod run in function at 10% withdrawn and annunctator at rod bottomed
- 21. Raise blade A to 2" and manually scram.
- 22. Raise blade B to 2" and tnp manual rcd run-in.
- 23. Raise blade C to 2" and scram by WRM tnp,
' 25.~ Annunciator board energized: horn on.
26, Jumper and tag log cleared or updated.
- 27. IRM recorder in fast speed.
- 28. Check magnet current for 90 ma on each magnet.
- 29. Cycle WRM range switch.
- 30. - Reset
- white rat" scram monitor.
- 31. Estimated entical blade position teorrected): inches.
- 32. Pre stanup 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. I I I 35. Reactor ready for startup.
Time (Completed)
Shift Supernsor/ Lead Semor Operator p
l Rev. 4/30/91 App'd iM SOP / A-ic l'
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DATE MODE - PROCESS DATA Time In Pool Ht. Ihch.
Pressuruer Level Pool Retl aP-PS 944 A PS 944B DPS 928A DPS 92SB DPS 929 Sec. T3 (6)
Sec. T e (5)
Sec. AT l
Sec. Water Flow Pool Tc Loop A (3)
Pool Tc L p B (4)
Sec. Th Pool A (7)
~
Sec. Th Prt. A (S)
Rx Cond in Rx Cond Out Pool Cond in i
.l Pool Cond Out Stack Gas l
Stack Part.
l Stack lodine Operator l l l l ader l l l l l l {
l ll l J l J ! I l l I I Heat Balance By l l l l l l l f l l l Manual Calculation: l l l l l l l l l l l l l l l Secuence rearrangeo oniy.
Rev. u 3 n / o1 Appd @ SOP /A-5b
1 l
)
PROCESS DATA Mode -- Date Time Pn, Flow A
- ,, '.sw b; Pool Flow A.
Pool Flow B Demin Flow A Demin Flow B Pn.Te Pn.T y.
Prt. AT Pool T e _
Pool Th' f
Pool AT North-Wall ARMS
]
West Wall ARMS l i South Wall ARMS
]
AIR Plenum 1 1
Secondary Water i
Dndge .
]
Fuel Vault 1
Room 114 i Air Plenum 2 l Fission Product i
TAA Yellow l TAA' Rod Run-In l TAA Green Rx Pressure l l l l l Rx Tc Loop A f l l f -
RX T c WPB I l l l l
' Fief. V30/9]Appd lipkrs ,
SOP /A-De
. = . .. _ _ . - .- . _ _ _ - . . - ..
1 REACTOR ROUTINE PATROL DATE: J
- 1. Time of start of patrol
- 2. Time and date all charts
- 3. Visual check of entire pool
- 4. Anti riphon tank pressure 36 psig 3 psi
- 5. North iso door seal pressure 18 28 psig
- 6. South iso door seal pressure 18 28 psig
- 7. 5th level backup doors open 8.16" iso viv A air pressure 45 55 psig 9.16" iso vlv B air pressure >90 psig
- 10. Emerg air compress on standby Bkr closed. Av open, cace 90-120 osic
- 12. Door-101 seal pressure 18 28 psig
- 13. BP floor Conditions normal
- 14. Fuel vault Locked
- 15. Inner airlock door seal pressure 18 28 psig
- 16. Outer airlock door seal pressure 18 28 psig
- 17. Cold deck temperature 45-65 deg F
- 18. Argon bank pressure >200 psig
- 19. Full N2 bottles Total > 3 )
- 21. Bank on service A or B ;
- 23. Bank A bottle pressure > 250 psig
)
- 24. Bank 8 bottle pressure > 250 psig .
- 25. N2 header pressure 135-145 psi j
- 26. T-300 level >2000 gal -
l l _
On the. first routine patrol of the day or the first patrol after a startup, drain all water from the anti-siphon system. If draining causes the pressure to drop signifi-
-cantly, return to the middle of the band (36 psig) and record tne pressure here. If a condition or reading is normal, enter a "V" (for conditions) or the reading in tne applicable' box. If the condition is abnormal. enter the condition or reading and circle it. Explain all abnormal conditions or readings in the REMARKS on page 3.
Rev a/30/91 App'd tVkik SOP /A-Ba
REACTOR ROUTINE PATROL DATE: -
- 27. T 301 level <6000 gal I
- 28. Labyrinth. sump Levet < Alarm Pt.
- 29. RO unit pcwer - og
- 30. RO unit temperature 24 28 C* or stby
- 31. RO unit pressure 190 200 osio or stby 32, UPS room '#O ^I*'** I'di* *'*d Thermostat >Ss CF Te -o 4 r* t-
- 33. T 300. T 301 Room '
em 40 F
- 34. Rm 114 particulate filter AP <3.5* water }
35a. EG. Rm. (Perform complete Thermostat >60* F (checklist on Sunday) Temp. > 50* F 35b. Battery charging current <1 amp 35c. Battery Voltage > 28 V 36, External doors Alliocked except east
- when sec. on duty
- 37. CT basin water level _ 5 10"
- 38. Automatic secondary makeup viv Auto or open 39, Acid day tank level Visible 40, Acid control and pH Range as posted
- 41. Blowdown control /cond. Range as posted
- 43. P pump (s) running =
- 44. Pump strainer aP 0 7.0 psi
- 45. Discharge pressure
- 46. Pump strainer aP 0 7.0 psi
- 47. Discharge pressure l
- 49. WT booster fan Running.
l
- 50. Fission product monitor flow 95 105 cc/ min l
- 51. viv control header pressure 90 -120 psig
- 52. Pressurizer N2 supply press 90 100 psig Rev.4/ 30/ 9I App'd %AVA SOP /A-8b
REACTOR ROUTINE PATROL DATE:
- 53. Check rm 114 from door
- 54. Deltech oil fiiter
- red level * < 75% dark red and blow down
- 55. Seal trench 61 66' Run pump on cay:,
_56 Waste tank #3 level
- 57. Waste tank #2 level
- 58. Waste tank #1 level
- 60. Time of completion of patrol
- 61. Operator initials RF.J/ ARKS:
Rev. L'~"' App'c h SOP / A-8C
STANDARD OPERATING PROCEDURES 2nd Edition Effective Date: 5/02/89 (Revisions #1 through #24 to the October 1981 printing were incorporated.)
Revision Number 5 Revision Date: June 6,1991 REACTOR EMERGENCY PROCEDURES REP-0-2 6/05/91 RE P 1 6/05/91 RE P 1 6/05/91 REP-20-2 6/05/91 REP 1 - 6/05/91 REP-20-3 6/05/91 RE P 1 6/05/91 REP-21-1 retyped only 6/05/91 REP 1 6/05/91 REP-21-2 retyped only 6/05/91 REP 1 6/05/91 REP-21-3 retyped only 6/05/91 REP 6-1 6/05/91 REP-22-1 6/05/91 REP 1 6/05/91 REP-8-1 6/05/91 REP 1 F/05/91 REP-9-2 6/05/91 REP-9-3 6/05/9; RE P-9-4 6/05/91 RE P 1 6/05/91 REP- l l- 1 6/05/91 REP- 12-1 6/05/91 REP- 12-2 6/05/91 REP 1 6/05/91 REP-13-2 6/05/91 REP 1 6/05/91 REP 1 6/05/91 REP- 15-2 6/05/91 REP- 15-3 6/05/91 REP- 15-4 6/05/91 REP 1 6/05/91 REP 1 6/05/91 RE P 1 6/05/91 REP 1 6/05/91 REP- 19-2 6/05/91 11-4
I REACTOR- !"RGENCY PROCEDURES 1hjEODUCT10N lt crinnot be overly stressed that the guideline for any emergency procedure shall be acuons which safeguard personnel and equ;pment in that order.
If, while operating die University of Missoun Research Reactor, a situation develops that requires an emergency action as set forth in these procedures, it must be remembered diat for a transient type accident.
Title 10 of tit Code of Federal Regula ions.Part 50.36. dictates certain acuons as pertairing to safety limits a i limiting safety system settings, in the case of a transient typ! accident, the Shift Supervisor must determine before resuming operation, if a safety limit, as illustrated by the safety limits set forth in the MURR Technical SpecificaUons, has been exceeded.
If, in fact, a safety limit has been exceeded, the reactor shall remain shutdown unul the Commission authorizes resumption of operauon.
Limiting safety system setungs are those setungs which will initiate automatic acuon to prevent exceeding a safety limit. If a safety system setting is exceeded without Teceiving an autualatic funcuan trip the reactor shall be shut down and the Commisson notified. The cause of the failure will be noted and correcuve action taken before operadons resume.
The follow.rg procedures audine actions to be taken by reactor operaung personnel. Immediate actions shall be completed as soon as possible, not necessarily in any order, to place the reactor 'n a safe condiuon. Subsequeat aedons can be completeted as ume allows or as the situaucn dictates.
Rev. E M App'd EM R E I' 2
l
,. l REP 1 FAD.URE TO SCRAM OR ROD RUN IN j IE for any reason, the reactor fails to scram or rod run in ;
automadcal'./ when called for by the protecuve system, the reactor !
- operator shall:
IMMEQJATE_ ACTION _5J
- 1. MANUALLY SCRAM the reactor, ensure the reactor is shutung down. verify all rods are bottomed. --__
SUBSEQUENT ACTIONS:
1._ Nodfy the Shift Supervisor, 2, Verify that safety limits and LSSS were not exceeded.
- 3. Determine what caused the reactor to fall to scram or rod run-in automadcally and correct the problem before resuming ,
operadon.
- 4. Make console entry and fill out UNSCHEDULED SHUTDOWN ;
REPORT.
t Rev. .nZ27 /o1 App'd M RE P 1 +
s
- + - . . , - . - - - ~ . . . , , . . - . - . _ _ _ . - . _ _ __,__.,-.,.,.m-..
REP 2 E.EACTOR SCRAM IMMEDIATE ACTIONS:
- 1. Ensure reactor is shutting down, verify all rods are bottomed.
- 2. Deternfine cause of scram and take corrective actions as required.
EUBSEQUENT ACTIONSJ
- 1. Notify Shift Supervisor.
- 2. Make console log entry and fill out UNSCHEDUI.ED SHUTDOWN REPORT.
Rev. iL27/91 App'd WMT RE P 1
REP-3 REACTOR SCRAM FROM LOSS OF PRIMARY SYSTFM PRESSURE OR FLOW IMMEDIAM ?d3TIONS:
- 1. Ensure reactor is shutung down verify all rods are bottomed.
- 2. Check that primary system is in nonnal shutdown lineup.
- 3. Check for temperature across in pool heat exchanger.
SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Place primary system switches and controls in nonnal shutdown lineup.
- 3. Make console log entry and fill out UNSCHEDULED SHUTDOWN REPORT.
Rev. 6 / 27 m1 App'd WWM R E P 1
-- e & :n evy - ,n---a -Pww ---?#p t
I BEP 4 IUGII RADIAT1QtLLfiVf1S IMMEDIATE ACTIONS:
- 1. Investigate the cause/ source of high radiation level.
- 2. Notify Shift Supervisor.
SUBSEQUENT ACTIONS:
- 1. Notify the Manager of Health Physics.
- 2. Notify Reactor Manager, if alarm point is exceeded.
- 3. Closely monitor the radiation level.
- 4. The Shift Supervisor may lower reactor power by MANUAL ROD RUN IN to reduce radiation levels.
5.1E reactor power is reduced, make console log entn and fill out UNSCHEDULED SHUTDOWN REPORT.
Rev. 6/27/91 App d WM RE P 1
l i
REP 5 NUCLEAR INSTRUMENT FAILURE IE any nuclear instrument channel required for operation
- is not functioning correctly and the reactor has not scrammed due to instnnnent failure, the reactor operator shall:
IMhtEDIATE ACTIONS:
- 1. MANUALLY SCRAM the reactor, ensure reactor is shutting down, verify all rods are bottomed.
EUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Make console log entry and fill out UNSCHEDULED SHUTDOWN REPORT.
- NOTE: ALL SLX NUCLEAR CHANNELS ARE REQUIRED TO BE OPERATIONAL FOR REACTOR STAT (l'UP: CHANNE!S 2 THROUGH 6 ARE REQUIRED OPERATIONAL DURING OPERATION AT POWER.
Rev. 6/2' '9'._ App'd .1AbT0\ REP-5-1
i BELG !
AREA RADIATION MONITORING SYSTEM (A,RMS) l EAE),lRE TO ACTUATE REACTOR ISOLATON f if the Area Radiadon Monitoring System (ARMS) monitor for Containment Air Plenum or Reactor Bridge fall to perform their reactor isolation function when required:
IMMEDIATE ACTIONS:
- 1. MANUALLY ISOLATE the _ containment building, ensure the reactor is shutung down, verify all rods are bottomed.
- 2. Verify containment has sealed as indicated by venuladon door and exhaust valve lights. -i
- 3. After ensuring all personnel have evacuated containment, the operator will exit containment, t
SUBSEQUENT.. ACTIONS;
- 1. Follow procedure FEP 2 for Reactor isolation.
- 2. Check remote radiadon indicadons in Room 282 (ET shop).
- 3. Perform remote air sampling of containment building as per -
- 4. Make console log entry and fill out UNSCHEDULED SHUTDOWN. ;
REPORT once containment access is reestablished.
4
, Rev. 6/ 27/91 App'd bWJO\ REP-6-1
I l
l BEE.Z LOSS OF COMMUNICATIONS BETWEEN REACTOR CONTROL ROOM AND EXPERIMENTERS l'
(DELETED 1 NOTE:- Since MURR has redundant paging capability (phone system or intercom), plus other options to maintain communicadons ;
(portable radio or telephone) with experimenters this emergency procedur ' is cancelled.
The communications requirements during reactor startup are detailed in SOP 1.4.3.1 Use of the Public Address System.
?
i 1
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Rev, 6/ 27/91 App d M REP 1 s Ee-- ---w -,- .'w.,-er..wa. e. ,.m , - ..,..- .... +-...- . ,n,.ymw-+,,, 4,-w-rrwer..,,.,,-rwi.w.r.,m,w,,,42, -rn,--,o,-m-,,-,-.ww+ - , v y-w<emgu --v- e+
REP 8 CONTROL ROD DEEE EAILURE / STUCK ROD lE the reactor operator detects a stuck or inoperative drive mechanism. he shall:
IMMEDJATE ACTIONS:
1, SCRAM the reactor, by placing master switch (ISI) in _TLSI ,
ensure the reactor is shuttJng down verify non affected rods are bottomed jSl]ESEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Note approximate stuck position.
- 3. Disconnect power to affected rod drive mechanism and install dumray load test connector.
- 4. Insert unaffected rod drive mechanisms manually.
- 5. Make console log entry and fill out UNSCHEDULED SHUTDOWN REPORT.
- 6. Make investigation of stuck rod after defueling two fuel positions.
Rev. 6/ 27/91 App d UJENA R E T'8- 1
i B.EP 9 t
ELECTRICAL ANOMALIES l i
NOTE: An anomaly such as single phasing or a reduction in line !
voltage may not be obvious. The reactor may or may not shutdown. Symptoms may incli:de dimming of lights, loss of !
some containment lights or loss of some process system i equipment. ;
A. SINGLE PHASING OR LOW LINE VOLTAGE t
in the event of a single phasing or low voltage condition, the ;
reactor operator shall:
i IMMEDLAIK_ACTJONS1
- 1. MANUALLY SCRAM the reactor /or if already scrammed, ensure the reactor is shutt.!ng down, verify all rods are bottomed.
5
- 2. Turn QEE all pumps and cooling tower fans in an expeditjous mminer.
- 3. Place all valve controls in their normal shutdown position and MANUAL mode.
- 4. Trip the auto transfer switch on substation "B".
t SUBSEQUENT ACTIONS:
1.- Notify the Shift Supervisor. !
Rev, 6/27 /91 App'd iN- R E P 1
- 2. Check emergency generator and its loads for proper optrauen.
- 3. Trip the supply breakers for MCC-1. MCC 2A and MCC 2B in cooling tower.
- 4. Invesugate cause of electrical anomaly.
- 5. If rabbit is in the reactor, transfer P-tube blower to emergency power and return the rabbit.
l 1
G. Make console log entry and fill out UNSCHEDULED SHUTDOWN i REPORT.
1 BECOVERY ACTIONS:
- 1. Check all three phases on each substauon for proper voltages.
- 2. When starung systems, closely monitor any equipment known to be running at the ume the electrical anomaly was noted.
- 3. A FULL POWER STARTUP CHECKSHEET shall be performed prior to starting up the reactor.
Rev. 6/?7 /ol App'd IM R E P-9 -2
l
- 3. SUSJAINED LOSS OF ELECTRICAL POWEll in the event of a sustained loss of power the reactor operator shall:
IMMEDIATE ACTIONS:
- 1. Ensure the reactor is shutting down, verify all rods are bottomed.
- 2. Turn QEE all pumps and cooling tower fans.
- 3. Place all valve controls in their normal shutdown position and tMNUAL mode.
- 4. Trip the master supply breaker on substation "B".
SUBSEQUENTACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Check emergency generator and its loads for proper operation.
- 3. Trip die supply breakers for MCC 1. MCC-2A and MCC-2B in cooling tower.
- 4. Check fuel tank level and project remaining run time of emergency generator.
- 5. Determine cause of electrical power loss.
- 6. If rabbit is in the reactor, transfer P-tube blower to emerger cy power and return the rabbit.
- 7. Make console log entry and fill out UNSCHEDULED SIIUTDOWN REPORT.
Rev. 627 / 91 App'd - M RE P-9-3
BECOVERY ACTIONE1
- 1. Check all three phases on cach substation for proper voltages.
- 2. When starting systems, closely monitor any equipment known to be running at the time the electrical anomaly was noted.
- 3. A FULL POWER STARTUP CHECKSiiEEr Shall be performed prior to starting up the reactor.
C. MOMENTARY LOSS OF ELECTRICAL POWER 1 NcE: When only a scram has occurred the reactor operator shall:
IMMEDIATE ACTIONSJ
- 1. Ensure the reactor is shutting down verify all rods bottomeo.
SUBSE9UENT ACTIONS:
- 1. Notify Shift Supervisor.
- 2. Verify momentary loss of electrical power with pawer plant.
- 3. The reactor may be operated after performing a REACTO'l SHORT FORM PRECRITICAL CHECKSHEIR
- 4. Make console log entry and fill out UNSCHECULED SHUTDOWN REPORT.
Rev. 6/27 / 91 App d \#IOt\ RE P-9--t
}
I REPe10 I
FAILURE OF EXPERIMENTAL APPARATUS !
Upon receiving reliable information that experimental equipment is !
operating in a manner hazardous to personnel and the hazard is due to radiation from the reactor, the operator shall:
i i
IMMEDIATE ACTIONS:
- 1. MANUAL ROD RUN IN to reduce power.
- 2. Secure the experiment or keep personnel away. !
SUBSEQUENT ACTIONS:
- 1. Notify Shift Supervisor. - I
- 2. If the problem cannot be readily corrected. SCRAM the reactor and return experitr.ent to a safe condition. ;
- 3. Repair experiment or place in a safe condition before restarting i the reactor. '
- 4. Make console log entry and fill out UNSCHEDULED SHUTDOWN I REPORT.
F i
-e i
- Rev. 6/27/91 App d libM RE P 1 l
9
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- - - _. -- . . -~ . - - . . . .-- . . _ _ . _ . . . . - . .
I REP.11 LOW FIRE MAIN PRESSURG IMMEDI ATE ACTIONS!
- 1. Send operator to fire main pressure gauge to determine pressure.
- 2. IE pressure remains below minimum pressure required by last Emergency Pool Fill Flow Test (CP-16), SIIUTDOWN the reactor.
SUBSEQLTNT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Determine cause for fire main low pressure.
- 3. Make console entry and fill out UNSCHEDULED SHUTDOWN REPORT.
k Rev. 6/27 /91 App'd l#$W\ REP- 11-1
. ._. __ -. _ _ . . _ _ _ . . _ _ . ~ . . . _ . - . . _ _._.. . _ _ _ _ . . _ . . _ . ,
l REP.12 LOSS OF DOMESTIC COLD WATER TO FACILITY l 1
}MMEDIATE ACTIONS: [
i
-1.- Send operator to monitor secondary sump level.
2,- Secure the Main Air Compressor.
i SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Monitor Nitrogen System pressure to ensure adequate supply for valve operation. .
- 3. Announce to the entire facility that domestic cold water service y has been interrupted.
- 4. IE service water cannot be restored within a reasonable amount of time, SHUTDOWN the reactor and secure primary coolant pumps.
- 5. Secure and tag out the following equipment:
i I
- a. Secondary pumps P1,P2.P3.and P4. after die reactor has been shutdown (P4 can be left on for building A/C support at the discretion of the Shift Supervisor).
- b. Vacuum Unit Pumps. _;
f i
Rev.16/27 / 9f App'd VRM REP-12-1 4
P 9
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+e . - ,2c wc-,rv-w m , .-,- m . m w w.ev-+- m - %-, e -w e i--r wn, ye w , w g +ny,-+,,+,g.-%-5,.m,-4 w,- w w + ,m- wrm yw vye.- =,=cv--v e evy w r w y -v e-,y-,+ v w w rvyywry g-w -v +r
- c. Air conditioning Units. (If all Secondary Pumps are secured.) l l
l
- d. Hot Water Recircing Pump.
- c. Room 212 (North counting room) air conditioner. 1 (Notify Research and Applications Group.)
- f. Room 232B (IWSRC Counting room) air conditioner, i (Notify Research and Applications Group.)
- g. Room 260 air conditioning unit. *
- h. Ice Machine.
- 1. Control Room Water lienter.
- 6. Make console entry that the machinery above has been tagged out as per REP 12. and fill out UNSCIIEDULED SliUTDOWN REPORT.
RECQYERY ACTIONS:
- 1. Upon restoration of water to the facility, return all systems to normal status.
- 2. Announce to entire facility the ret.toration of domestic cold water service.
Rev. C/27 /91 Appd AY/m, I REP-12-2
_ - . _ _ _ . -- . . . . . . - - - . _ _-- - __ - - ~
l l
RE.P 13 f&MPLETE OR PARTIAL LOSS OF SECONDARY Ft.OW IMMEDIATE ACTIONS:
- 1. Swtich secondary cooling pumps to determine whether action restores flow.
- 2. LE atandby pump cannot be put on line, during a complete loss of flow, reduce reactor power to less than 100kw.
- 3. Send an operator to Ole cooling tower to assess the flow reduction problem. "
- 4. Monitor the position of S-1 and reactor temperatures.
SUBSEQUENT ACTIONSJ
- 1. Notify the Shift Supervisor.
- 2. Determine cause of flow reduction and detennine effects on further operation.
- 3. Make console log entry and fill out UNSCIIEDULED SHUTDOWN REPORT, if reactor is shutdown.
" 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.
Rev. 6/27!91 App'd WM REP 1
l r
- c. A break in the secondary cooling line,
- d. Low cooling tower sump level switch tripped.
- f. Restriction in flow due to faulty discharge check valve. .
- g. Clogged suction strainer.
i t
t t
Rev. 6/27/91 App'd M REP-13-2
REP- 14 LOSS OF POOL FLOW DURING REACTOR OPERATION
_ IE pool flow rate drops below 500 gpm in either loop for an unspecilled reason, the react ~or operator shall:
IMMEDIATE2CTIONS:
1., MANUALLY SCRAM the reactor, ensure the reactor is shutting down, verify all rods are bottomed.
- 2. Shut down the pool system, leaving the primary and secondary systems on line.
SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
- 2. Determine the cause of pool flow loss and correct it before restarting the reactor.
3.- Make console log entry and fill out UNSCHEDULED SHUTDOWN REPORT.
Rev. 6/27 /91 App'd IMTV\ REP-14-1 9 d +9-cwg1, e19hynr+m-y 4r*W-qg-e-g_"
REE:la .
LOSS OF POOL WATER DURING REACTOR OPERAMON i E the pool level becomes less than the ROD RUN IN limit (-20ft.)
and continues to recede die operator shall:
IMMEDIATE ACTIONS: !
- 1. MANUALLY SCRAM die reactor, ensure the reactor is shutting !
down verify all rods are bottomed. j
- 2. Secure P508A and B and verify vidve 509 closes automatically, close manually if necessary. -
- 3. Secure P513D.
- 4. Close valve 547 by actuating the manual 3 way valve on upper bridge level, ensure valve indicates shut. j At this point, the pool is isolated from the process leg of the poc!
cooling system.
CAUTION: Increased radiation levels due to low pool level may cause a reactor isolation. Evacuate all personnel except FEO members from containment.- This type of emergency may ;
have consequences severe enough to warrant voluntary emergency level exposures up to 25 rem by FEO personnel ,
to mitigate the consequences to the general public.
Monitor radiation levels closely for radiation dose j assessment.
S.UBSEQUENT AQTIONS:
.1. Notify Shift Supervisor
- 2. . E pool level stops decreasind, continue with section (A). E level continues to decrease, go to section (B).
Rev. 6/27/91 App'd M REP 1 i
F
A. Lean.ON PROCESS SIDE OF V500
- 1. Enter room 114 observing proper radiation protectjon.
- 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: TIIE PIPE TRENCH AND LADYRINTil SUMP VOLUME (TO A HEIGHT EQUAL TO THE TOP OF PIPE TRENCH) IS APPROXIMATELY l4.000 GALLONS.
- 4. If the pool level had receded to a point that a higher than normal radiation level was created on the bridge, water fonn T300 and T301 should be added to reduce the radiation levels.
- 5. Perform recovery actions as per section (D).
B. LEAN INSIDE V509 OR THRQUGH BEAMPORTS
- 1. Activate the FEO as per SEP-1.
- 2. Isolate containment of all but FEO members.
- 3. Check beamport floor and room 114 tunnel to determine the source of the leak.
- 4. E the leak is through the beamports go to Section (C). E the leak is inside V509 continue:
- 5. Ccr. tin.te to operate the primary system and secondary system. If 0411b2
- 6. Fecure the tunnel and cooling tower sump pumps, Rev. 6/ 27/91 Appd WATA REP-15-2
i
- 7. Efforts should be made to contain the leakage in the room 114 pipe trench, die labyrindi sump and waste tanks (i.e., secure labyrindi sump pump when waste tanks are full).
NOTE: THE PIPE TRENCII AND LABYRINTH SUMP VOLUME IS APPROXIMATELY 14,000 GALLONS.
- 8. If leak cannot be secured, and a core void is suspected, open die emergency pool fill valve under die floor plate at the pool edge to open. This will commence filling the facility to die ground level (covering the core),
- 9. Perform a facility evacuadon.
- 10. Perform recovery aedons as per secdon (D).
C. gAK TIIROUGII DEAMPORT
- 1. Isolate containment of all but FEO members.
2, Continue to operate the primary and secondmy systems.
- 3. Secure the tunnel and cooling tower sump pumps.
- 4. Efforts should be make 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).
5, Observing proper radiadon protecuan, begin dismantling the experiment at the suspected beamport so attempts to stop the leak can be perfonned.
- 6. Perform recovery actions of secdon (D).
D. RECOVERY FROM SIGNIFICANT POOL LEAK
- 1. Repair cause of leak.
Rev. M27 /91 App'd UMM REP-15-3
.- . - . . . _ . - . - _ . . . - . - - . - . . - . - , - ... ... -. . - ~ . . . - _ . . - . . . .-
1 1
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- 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 APPENDIX 11. ,
i c
4 4
i Rev, 6/27/91 App'd L%7% REP-15-4
I l
i REP.16 I
REACTOR LOOP ISOLATION VALVES f 507A & 507BJ l FAIL TO CLOSE AUT_QMATICMLX IE these valves fail to close automatically the reactor operator shail:
l IMMEDIATE ACTIONS: f i
- 1. Place Master Control Switch (1S1) in I_ cit. l 2.' Place 507A/B AUTO / MANUAL switch in Manual.
- 3. P! ace the OPEN/CLOSE switch in Close. ;
SUBSEQUENT ACTIONS; 4
- 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 I OUT OF POOL LEAK IN THE PRIMARY SYSTEM. CHECK VALVE 502 BACKS UP THE FAILURE OF 507B PREVENTING DRAINING OF THE CORE AND THE ANTlSIPHON SYSTEM PREVENTS CORE DRAINING IN CASE OF 507A FAILURE. [
i 9
- Rev. 927 /01 App'd NWA RE P-l G- 1
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REP 12 i
PRESSURIZER VALVES FAIL TO OPERATE I l
In the event of malfuncuan of any pressurizer valves: i l
IMMEDIATE ACTIONSI
- 1. SHUTDOWN the reactor.
- 2. Close the appropriate manual isoladon valve in line with the failed valve.
AIUtGE.QUER.T.AC1LORSi
- 1. NotJfy the Shift Supervisor,
- 2. Determine the cause of the malfunction and correct before resuming reactor operation.
- 3. Make console enuy and 1111 out UNSCHEDULED SHUTDOWN REPORT.
Rev. 6/ 27/91 App'd M
~
REP-17-1 .
d
[
- _. . _ _ _ _ _ .. _ .. _ . _ _ . _ _ - . _ ~ . _ .. _ _. _ . _ . _ _ - ., _ _- s ,
I 4
REP.18 BOTH ANTISIPHON VALVES f 543A & 543B 1 !
FArr TO OPEN AUTOMATICALLY l
thDdEDIATE ACT10NSt -,
- 1. Open 543A or 54313 manually with T wrench.
P
- 2. If unsuccessful, close the air supply valve and disccsnnect ,
copper tubing on the valve side of 3 way solenoids for 543A or 543B.
- 3. If the valve has not opened. again use the T-wrench to manually open the valve.
- 4. If all attempts fall to op,a cither valve and a core void is suspected, carry out the Reactor isolation Procedure (FEP 2). t SUBSEQUENT ACTIONS:
- 1. Notify the Shift Supervisor.
t 1
- NOTE: EITHER VALVE . (543A OR 543B)- WILL PERFORM THE !
DESIRED FUNCTION, FAILURE OF THESE VALVES TO OPEN :
PRESENTS A PROBLEM ONLY IN THE EVENT OF A PIPE RUFTURE.
Rev. 6/27/91 App'd ,$%_ REP-18-1
b i
REP _LH i EMERGENCY CORE COOLING VALVES ( 546 A/B 1 i FAIL TO OPEN AUTQMATICALLY l A. BOTH VALVES FAIL TO OPEN AUTOMATICALLY FOLL_OWING l
. SCRAM FROM LOSS OF FLOW OR PRESSURE. :
IMMEDIATE ACTIONS:
- 1. Place Master Control Switch (ISI) in Is11
- 2. Place Valve 54GA & 54GB AUTO / MANUAL switch in Manual
- 3. Place Valve 546A/B OPEN/CLOSE switch in Open.
IF the valve or valves have still not onened: *
- 2. Open the valve manually with T wrench.
- 3. If unsuccessful, close the air supply line to the valve (s) at the bridge and disconnect copper tubing on the valve side of the 3-way solenold. l
- 4. If the valve has not opened, again use the T wrench to manually
. open the valve. f
- 6. If all attempts fall to open one of the valves, operate the primary and secondary systems. >
. SUBSEQUENT ' ACTIONS: l
.l. Notify Shift Supervisor.
Rev. 6/ 27/91 App'd M REP-10-1
,,,,ne L-,v-e v. - v c w ,n~,w w w e- e , ,w---w,,v -r-sw-+-a,-m-v-ww.e , ew-, me- , m, 'ye--- >,--ev--- ,,m-=--
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B. ONE OR BOTH VALVES FAIL OPEN DURING OPERATYON 1E inu.cauon is received that one or both valves have opened and the reactor bt not scrammed *: the reactor opetator shall:
IMMEDI ATE ACTIONS:
- 1. MANUALLY SCRAM the reactor, ensuce the reactor is shutting down, vedfy all rods are bottomed.
SUBSEQUENT ACTIONS:
- 1. Notify ihe Shift Supervisor.
- 2. Make console entry and fill out UNSCHEDULED SHUTDOWN REPORT.
' NOTE: IF 546A/B OPENS DURING OPERArlON, A FLOW PATH FOR THE PRIMARY COOIANT BYPA*CING THE CORE IS ESTABLISHED (ABOUT 30-D's v t ORIGINAL CORE FLOW).
THIS REDUCED FLOW Wil. NUr LAD TO CORE DAMAGE SO LONG AS NORMAL TEMPERATURE PCWER AND PRESSURE ARE MAINTAINED. THIS REDUCED FLOW RATE, HOWEVER. DECREASES OUR SAFETY MARGIN FROM THE SAFETY LIMIT CURVES BY ABOUT 60%. SO THE REACTOR IS TO BE SHUTDOWN UPON RECEIPT OF THIS ACCIDENT (THE CORE DP SCRAM DPS 929 SHOULD HAVE INITIATED AUTOMATICALLY BY ONE OR BOTH 546 VALVES OPENING).
f<ev. 6,27 / 91 App'd U/ITN\ REP-19-2
REP 20 HIGH ACTIVITY LEVELS IN THE PRIMARY COOLING SYSTEh1 Upon receMng indication of an abnormal high level of radioacuvity in the primary cooling system, the reactor operator shall:
IMMEDIATE ACTIONS:
- 1. MANUALLY SCRAM tlle reactor, ensure the reactor is shutting down verify all rods are bottomed.
SUBSRQ. U ENT ALUONS:
-1. lu". r ,e Shift Supervisor.
- 2. . . t't i aager of Health Physics.
t
- 3. M en!" stack monitoring system indications closely to determine if an v-nt should be classified as per Site Emergency Procet. Jes. Use guidelines in REP-21. High Stack Monitor Indications.
4.' -
Precautionary reduction of flow - secure one pump to decrease flow by one-half.
NOTE: - THIS ACTION ASSUMES WORST CASE CONDITION,
- A FUEL ELE"IENT FAILURE. THE REDUCED FLOW.
IS TO MINIMIZE PLATE EROSION.
- 5. - Determine the source of radioactivity and magnitude of activity
- by:
- a. Checking fission product monitor.
Rev. 6/27/91 App'd OD REP-20-1
=-
- 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. '
WARNING: EXTREME CAUTION SHOULD DE OBSF.RVED WHEN ENTERING AREAS CONTAINING PRIMARY COOLANT. l THESE AREAS SHOULD DE MONITORED BY HEALTH l PHYSICS BEFORE ENTRY. ADEQUATE PROTECTIVE l MEASURES SHOULD DE TAKEN BEFORE ENTERING THESE AREAS.
i G. IE the source of activity is determined to be ilssion products. j the primary cooling system should be shutdown as per SOP IV.2. l 1
7 Identify the leaking or ruptured fuel element. The fuel element which is leaking f1ssion 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 personnel 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" basket,
- c. Move each fuel element from one of the baskets to the fuel inspection rig for visual inspection.
- d. 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.
Rev. 6/27'o1 App'd OM REP-20-2
2 4
- e. The Reactor Manager will determine the disposition of the '
leaking fuel element.
- f. Clean up contaminated primary cooling system by leaving the primary cooling and primary demineralizer loops in operation.
, s. Make console entry and 1111 out UNSCHEDULED SHUTDOWN REPORT.
Rev.A/onc1 App'd M REP-20-3
- . - - ..~ - . .---.- . ~ . ~ . ~ . ~ . . . ~ - - - - - _ . - . - - - . - - .
REP 21 r HIGH STACK MONITOR INDICATIONS DDfEDIATE ACTIONS:
, 1. Notify the Shift Supervisor.
- 2. Notify the Manager of Health Physics After working hours contact: HEALTH P!WSICS CALL LIST. ,
SUBSEQUENT ACTIONS:
- 1. Evaluate the extent of iodine and Darticulate levels with overlay
- 1. and gas, with overlay II. If the extent of radioactMty is great enough to. enter event classifications the highest category of event' indicated by gas, lodine or particulate reading will be used to. classify the event.
A. TODINE and PARTICULATE: (overlay Il Check the stack monitor reading with overlay I. The ranges of values represented on the overlay are the threshold levels of ,
concentrations corresponding to specific emergency events in excess of Technical Specification-limits.
The overlay thresholds assume the present release rates will be-
- constant for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. They are conservative, since the pre'sent release rate may exist for less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the
- emergency action levels are:
UNUSUAL EVENTS - 3800 MPC averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ALERT EVENTS -
19.000 MPC averaged over 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-SITE AREA EMERGENCY - 95.000 MPC averaged over 24
-hours (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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: therefore still have 3800.MPC averaged over 24
- hours)
These overlays are to graphically assist the operator's judgement as to the extent of release.
Rev. 7/03/85 App'd % REP-21-1
' Retyped Only 6/27/91 4
h-- e- u,e e ,- . - - , . .,,r -.-% y-. w.u. ,-4,,--, , - - . . q .... + . , 7.~.r--
THE FOLLOWING IS RETYPED INFORMATION ONLY)
B. cum (Overlay li)
- 1. E gas concentration exceeds 3.3. X 103CPM (3800 MPC) but less than 1,66 X 104CPM (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.
- 2. E gas concentration exceeds 1.66 X 104 (19.000 MPC) but less than 8.3 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.
- 3. E gas concentration exceeds 8.3 X 10 4CPM (95,000 MPC) but less than 1 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 no evidence of declining, the event shall be classified as a SITE AREA EMERGENCY.
- 4. E gas concentration reaches full scale and remains there for 10 minutes without decline and cannot be attributed to electronic failure, the event shall be classified as SrrE ARE EMERGENCY.
- 5. E gas concentration shows no signs of leveling off or declining, determine 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:
CPM 24 HOUR AVE = AVE 30 MIN READING (CPMI as 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 (in CPM) X INTERVAL TIME Dl' RATION (MIN)
Ghb} m Agg= fIBUN/HR) 24 HOURS or simplilled CPM 24 HOUR AVERAGE "
AVE INTERVAL READING (CPM) X IN*TERVAL TIME DURATION (MIN) 1440 -
Rev.1L03/89 App'd bM REP-21-2 Retyped On'iy 6/27/91
EVALUATION OF IODINE / PARTICULATE CONCENTRATION TIME DURATION OF RISE (MINUTES)
COUNTS /itINUTE l
INDICATED 5 10 15 20 25 30 35 40 45 50 55 60 l
+
LA]_ _ . _
UNUSUAL EVENT 2.5x10 4 5x104 7.5x104 1x105 1.25x105 1.5x105 1.75x105 2x105 2.25x105 2.5x105 2.75x105 3:105 (3800 MPC)
I l
LBJ '
5 l ALERT 1.25x105 2.5x10 '3.75x105 5x105 6.25x105 7.5x105 8.75x105 1x106 (19000 MPC) (Full Scale)'
SITE AREA 6.25x105 1.25x106 EMERGENCY (> Full (95000 MPC) Scale) t for example: [A] A rise of 5 x 104 CPM in 10 minutes would correspond to 3800 MPC.
[B] A rise of 2.5 x 105 CPM in 10 minutes would correspond to 19000 MPC.
i NOTE: KEEP IN MIND TilAl THESE lHRESil0LD LEVELS OF CONCENTRATION WOULD HAVE TO EXIST CONTINUOUSLY FOR 24 IiOURS TO DE CONSIDERED A 24 HOUR AVERAGED CONCENTRATION.
Orig. 7/3/85 App'd I/
Retyped Only 6/27/91 A
~
7 w
. .. . . _ . _ . _ _ -. _ ~. _ _. .- . _ . _ _ _ _ _ . _ _ ___ _ __. _ .
t
_ REP-22 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 reactor operator shall:
IMMEDIATE ACTIONS:
- 1. SHUTDOWN the reactor immediately.
- 2. Secure the master control-switch.
- 3. Notify the UNIVERSITY POLICE by telephone.
- 4. Insure all doors are secure with priority to the truck entry door
- and personnel airlock door.
- 5. Facility evacuation or partial evacuation may be used to remove persons from affected areas.
SUBSEQUENT ACTIONS: .
- 1. Notify the Shift Supervisor.
- 2. 'Make console entry and fill out UNSCHEDULED SHUTDOWN REPORT.
NOTE: -FACILITY STAFF SHOULD NOT ENTER ANY DIRECT CONFLICT EXCEPT WHEN NECESSARY FOR THEIR OWN PERSONAL' .
= SAFET{.
Rev 6/27/91 App'd M REP-22-1
MURR SITE EMERGENCY PROCEDURES AND
~
- FACILITY EMERGENCY PROCEDURES Revision Number 6 Revision Date: July 11,1990 Section Page Number Number SEP-2 3 SEP-3 3 SEP-4 3 SEP 7 2-EMERGENCY CALL LIST FEP- 1 .5 Date Change Only FEP-1 6 Date Change Only FEP- 1 7 Date Change Only FEP-3(a) 1 New II-5
.. ~. . _ ~ . _ ._
SEP-2 (Cont'd) Page 3 of !.
TABLE 11 iMERGENCY SUPPORT ORGANIZATIONS
- a. UMC HEALTH PHYSICS SERVICES In the event of a radiological emergency, the U?tC Health Physics Services may be contacted to assist in checking facility personnel for contamination. After hours the Watch Office may be contacted to open the Research Park Development Building (backup emergency control center).
One of the persons listed below will man the backun control center.
CONIACT Office Hone Dr. Philip Lee 082-7221 445-5275 Jamison Shotts 882-7221 474-2194 David Spate 882-7221 657-9450
- b. UMC POLICE The UMC Police may be called to restrict entry 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the facility. 882-7201
- c. UNIVERSITY OF MISSOURI HOSPITAL AND CLINICS (UMH&C): Emergency Services 882-6003 ]
Ambul ance 882-6128 or 9-911 )
Walk-In (Emerg.C.) 882-8091 ]
The UMH&C snould be contacted in the event of personal injury, la tne event of personal conta,nination -or radiation exposure without injury, see MEDICAL EMERGENCY PROCEDURES.
If three or more personnel are involved, ask the Administrator-0n-Duty to implement the Radiation Disaster Plan. Refer to the MEDICAL EMERGENCY PROCEDURES for details.
- d. MU NEWS BUREAU See SEP-7, PUBLIC This office will initially. deal with questions- INFORMATION from offsite. Direct any questions from media to PROCEDURE this office. They will release statements only by EMERGENCY DIRECTOR authorization.
le . COLUMBIA FIRE DEPARTMENT 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9-911 ine Columbia Pire- Department snall De notifiec in the event of fire or neea of emergency rescue capability. Insure Office of University Relations is also called.
Rev. 7/11/90 App'c M
.- - -=- - -__ - . -. -
SEP.-3 (Cont'd)- Page 3 of-6 TABLE 111 EMERGENCY SUPPORT ORGANIZATIONS
- a. UMC-HEALTH PHYSICS SERVICES In the event of an ALERT condition, the UMC Health Physics Services may Lbe contacted to man the backup emergency control center.
After hours, call the Watch Office to open RPDB.
CONTACT Office Hone Dr. Philip Lee 882-7221 445-6275 Jamison Shotts 882-7221 474-2194 David Spate 882-7221 657-9450
- b. UMC POLICE The UMC Police may be called to restrict . entry 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the research park and to assist in partial site 682-7201 area evacuation if oeemed- necessary.
- c. UNIVERSITY OF MISSOURI HOSPITAL AND CLINICS (UMH&C): Emergency Services 882-6003 ]
Ambulance 882-6128 or 9-911 ]
Walk-In (Emerg.C.)' 882-8091 ]
The'UMH&C should be contacted in the event of personal injury. In the event of personal contamination or radiation exposure without injury, see MEDICAL EMERGENCY PROCEDURES.
. If three or more personnel are involved, ask the Administrator-On-Duty to implement the Radiation Disaster Plan._ Refer to the MEDICAL EMERGENCY PROCEDURES for details,
- d. MU NEWS BUREAU See SEP-7,
. . PUBLIC This office will' initially deal with questions INFORMATION from offsite. Direct any questions from media to PROCEDURE tnis office. They will release statements only by EMERGENCY DIRECTOR authorization,
- e. COLUMBIA FIRE DEPARTMENT 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9-911 Tne Columbia Fire Department snall De notified in tne event of fire or neec of emergency rescue capability. Insure Office of University Relacions is_also caliec.
Rev.'7/11/90 App'o (AMTh
.. . .- . ~ . - - . - - ~ . . --- .-
l SEP-4 (Cont'd) Page 3 of 6 !
TABLE IV EMERGENCY SUPPORT ORGANIZATIONS
- a. UMC HEALTH PHYSICS SERVICES In the event of a SITE AREA EMERGENCY, the UMC Health Physics Services may be contacted to man the backup emergency control center.
After hours, call the Watch Office to open RPDB.
CONTACT Office Home Dr. Philip Lee 882-7221 445-5275 Jamison Shotts 882-7221 474-2194 David Spate 882-7221 657-9450
- b. UMC POLICE The UMC Police may be called to restrict entry 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the research park and to assist in partial site 882-7201 area evacuation if deemed necessary.
C. UNIVERSITY OF MISSOURI HOSPITAL AND CLINICS (UMH&C): Emergency Services 882-6003 ]
Ambulance 882-6128 or 9-911 ]
Walk-in (Emerg.C.) 882-8091 ]
The UMH&C should be contacted in the event of personal- injury. In the event of personal contamination or radiation exposure without injury, see MEDICAL EMERGENCY PROCEDURES.
If three or more personnel are involved, ask the Administrator-0n-Duty to implement the Radiation Disaster Plan. Refer to the MEDICAL-EMERGENCY PROCEDURES for details, d.- MU NEWS BUREAU See SEP-7, ]
PUBLIC Tnis office will initially deal with questions INFORMATION from offsite. Direct any questions from media to PROCEDURE this office. They will release statements only by EMERGENCY DIRECTOR authorization.
- e. COLUMBIA FIRE-DEPARTMENT- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9-911 Tne Columbia Fire Department shall be notifiec in the event of fire or need of emergency rescue capability. Insure Office of University Relations is also called.
Rev. 7/11/90 App'd { LCyn'
SEP-7 (Cont'd) Page 2 of 4
- 5. The MU News Bureau staff member contacted should verify a call concerning an emergency at the University of Missouri Research Reactor by calling 882-4211 or E74-4119 and ask to speak to a member of the Facility Emergency Organization (FE0). If the person answering the phone does not know wno is in the FEO, tnen ask for anyone from the Director's i Of fice, Operations, Health Pnysics, 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 cmergency call can be verified.
VERIFICATION LIST F0P. MURR EMERGENCIES Name Soc. Sec . No. Name Soc. Sec . No.
Chuck Anderson Sue Langhorst Joe Baskett Charlie McKibben Rita Bonney Walt Meyer Kenneth Beamer Steve Morris Barry Bezenek Phil Neel Joe DeMers Leslie Powell Chester Edwards Mike Randolph John-Ernst Bill Reilly Christine Errante Tony Schoone Mac Evans Jim Schuh Les Foyto Tom Seeger John Fruits Vickie Spate Greg Gunn Ray Stevens Robert Hudson Mark Stumbaugh Rolly Hultsch ]
Nolan Tritschler Brenda Johnson Robert Walker Vernon Jones Mike Wallis Mike Kilfoil Tim Warner Ron Kitch Burle Warran
-6. MU News Bureau personnel contacted will determine the need for staffing and equipping an emergency information center and will call in the required staff and arrange for necessary facilities.
- 7. , MU News Bureau personnel will inform news media and others of the public, as necessary, of the emergency.
S. If possible, a MU News Bureau staff member will be sent on site to assist the EMERGENCY DIRECTOR with the release of information.
Rev. 7/11/9C App'c M
ENERGEf4CY PROCEDURE-Ef1ERGEllCY CALL LIST Ilealth Physics ___
_ Operations Emergency Supp gt_ Organ _ita,tions __ _ _
Phone fio.
Phone fio. Phone ik).
S. Langhorst 442-3534 M. Evans 698-2450 Uf1C Police 882-7201 !
R. Stevens 442-2539 K. Beamer 682-5499 !
J. Ernst 445-5621 R. Kitch 696-3710 Columbia Fire Department 9-911 J. Dellers- 443-4938 C. Kribbs 682-3980 1
ft, Stumbangh 564-2154 ] Ut! flospital and Clinics T. Seeger 875-8656 Emergency Services 882-6003 ]
J. Baskett 474-2046 Ambulance 882-6128 or 9-911 ]
Director's Office Walk-in (Emergency Center) 882-8091 ]
Phone lio.
S. Morris 445-4211 Uf1C Health Physics (Office) 882-7221 J. C. McKihben 44?-6728 Dr. Phil Lee (Home) 445-52/5 Jamieson Shotts (Home) 474-2194 David Spate (liome) 657-9450 Opera t ions .
Reactor Chemistry, Phone Tk). Phone fio. fill flews Bureau 832-6211 W. A. Meyer 442-7675 11. Glascock 474-8390 See Public information 832-6214 C. Edwards 443-1529 J. Schuh 874-3086 Procedure for other o r.
T. Schoone 443-8862 V. Spate 657-9450 PSone numoers. (SEP-7) 882-9142 R. Unitsch 442-6653 State Emergency flanagement C. Anderson 696-5506 Agency (SEftA) 314-731-2743 B. Bezenel 445-5680 G. Gunn 8/5-1162 f1RC, Region III 708-790-5500
- fl. Iritschlor 474-9388 ~
American fluclear Ir.surers 203-677-7305 3 L. Foyto 446-0491 J. Fruits 474-0774 j R. Hudsno 875-0451 V. Jones 445-2543 ft. Eilfoil 449-2524 P. fleel 442-8693
- 11. Randolph 442-5315 R. Walker 445-8077 M. Wallis 443-8764 T. Warner 816-882-6740 B. Warren 443-4938 ]
Rev . 7/l l/90 App'd hv3yyx !
!_E.P_-J. ( C on t ' d ) Page 5 of 7
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C0fiTROL ROOM RESPONSE TO ALPHA LABORATORY FIRE NOTE: Throughout this procedure continue to monitor stack exhaust monitor, Alpha Laboratory exhaust monitor (ALPHA-6) or Alpha Laboratory room tonitor (ALPHA-3) for' indication of airborne radioactivity, as apprupriate.
-1. -If a fire is detected by fire alarm or reported in tne Alpha Laboratory, the shift supervisor (or Senior licensed person in control) will call the Columbia Fire Department.
- 2. Tne shift supervisor will activate the Facility Emergency Organization by page system and provide warning to stay clear of facility basement.
- 3. The Emergency Director will detennine nature and specific location of fire (i.e., if fire .is in glove box or equipment exterior to glove box).
- 4. If fire cannot be put out immediately with local fire extinguishers, the reactor will be shut.down to focus attention on the fire.
- 5. Ensure Alpha Laboratory doors are shut and personnel are out of the laboratory.
If_ no experimenter.is present, call the cr.-call experimenter as soon as time permits.
- 6. Secure EF-13 and EF-14 at breaker on emergency distribution center.
- 7. -Secure.f acility supply and exhaust f ans at MCC-3 and check all fire doors closed.
- 8. Secure electrical power to Alpha Laboratory at breaker 17 on 120/208V distri-
.bution center and breaker 2 on emergency distribution center.
NOTE: This will secure Alpha Laboratory supply and exhaust fans.
- 9. Isolate Alpha Laboratory by closing supply and exhaust dampers, if possible. .
- 10. The EMERGENCY DIRECTOR -(or his delegate) should contact Fire Department-outside of facility to provide specific information.
- 11. The EMERGENCY DIRECTOR will stay in contact with INCIDENT COMMANDER to coordinate' fire fighting and life saving efforts. .
- 12. - Contact MU News Bureau to handle release of public information.
New 7/11/90 Appi a th
. _ . _ . _ _ - . _ . __. _. . _ . _ _ . . _ _ . - . _ __ _ ._. . - _ ~ - - _ . _ _ _ . . . - - _ - _
- MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES
' Revision Number 7 Revision Date: April 8,1991 Section Page Number Number SEP-2 2 SEP-2 5 SEP-3 2 SEP .6 SEP 4 2 ,
- SEP-4 6 SEP-7 2 -
SEP-l l l' EMERGENCY CALL LIST WORKSHEET C FEP-1 5 FEP-3 1 FEP-3(a) 1 II-6
SEP-2 (Cont'd) Page 2 of 5
-5. Send operator to west tower with radiation monitor to:
NOTE: Communicate by intercom, since stack monitor is affected by portable radio RF.
- a. Verify radiation background at stack monitor,
- b. Verify control room readings. 1
- c. Mark initial needle positions on analog display with the time for future analysis if the control room display becomes inaccessible.
- d. Verify flow rate through monitor is 7 1 SCFM. If not, use Worksheet A to determine stack monitor values.
- 6. If nuclides which are being released are in doubt, pull stack filters and analyze.
- 7. The EMERGENCY COORDINATOR shall evaluate the need to evacuate specific portions of the facility.
- 8. The EMERGENCY COORDINATOR shall appoint and have a surveillance team check any areas evacuated in step 7, clear of personnel within 30 minutes.
NOTE: EMERGENCY DIRECTOR approval required for any voluntary radiation exposure in excess of 10CFR20 limits. (Up to 75 rem for life - ]
'saving, up to 25 rem to prevent exposure to members of general public in excess of I rem whole body and 5 rem thyroid.)
- 9. The EMERGENCY DIRECTOR shall determine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if needed, activate them or place them on standby.
See Table II, EMERGENCY SUPPORT ORGANIZATIONS.
NOTE: If 9-911 is called during any emergency, contact MU News Bureau.
Rev. 4/08/91 App'd IM
SEP-2 (Cont'd) Page 5 of 5
- d. LABDRATORIES
( 1) Deterrnine which laboratory is the source of release, by decking radiation levels in quadrant exhaust ducting.
(a) Southwest Quadrant (b) Northwest Quadrant (c) Northeast Quadrant ACTIONS TO CONSIDER
( l) Throttle flow from laboratory quadrant to reduce release rate to less than Technical Specifications limits.
(2) Area Evacuations UBSEOUENT ACTIONS:
5
- 1. Change s'ack filters when chart reading exceeds 3 x 10 cpm Reevaluate chart reading to determine if release rate is increasing / decreasing. Record time of filter changeout.
- 2. Evaluate results of correction and subsequent actions to determine need to escalate /de-escalate the emergency classification.
- 3. Keep record of actions and evaluations and time they were done for documentation. Use procedure wcrksheets.
- 4. Notify NRC, Region III, that an UNUSUAL EVENT has occurred within one hour after event is classified or reciassified. (Use Worksheet C)
- 5. Notify American Nuclear Insurers (ANI) [203-677 7305] that an UNUSU.AL EVENT has occurred. (Use information in Worksheet C) ]
- 6. Notify State Emergency Management Agency (SEMA) [314-751-2748] that an UNUSUAL EVENT has occurred. (Use information in Worksheet C) ]
RECOVERY ACTIONS.-
- 1. Evaluate potential radiological effects to onsite and offsite personnel before returning access to specific areas effected by UNUSUAL EVENT emergency.
- 2. Procedures shall be written and approved for handling significant recovery evolutions.
NOTE: During recovery operations, personnel exposures to radiation should be maintained within 10CFR20 limits.
Rev. 4/03/91 App'd M
SEP 3 (Cont'd) Page 2 of 6
- 5. Send operator to west tower with radiation monitor to:
NOTE: Cornmunicate with intercom, since stack monitor is a'fected by portable radio RF.
- a. Verify radiation background at stack monitor.
- b. Verify control room readings.
- c. Mark initial needle position on analog display with time for future analysis if control room display becomes inacces,ible.
- d. Verify flow rate through monitor to 7 1 SCFM. If not, use Worksheet A to determine stack monitor values.
- 6. Pull stack monitor filters and analyze.
- 7. After determining radionuclid responsible and verifying concentrations greater than 19,000 MPC (a) secure EF-13 and EF-14; (b) secure RF2, SF2, RF1, SFl; (c) secure all individual vent fans.
- 8. The FMERGENCY COORDINATOR shall evaluate the need for a partial or total evacuation of the facility.
NOTE: For facility evacuations or northeast quadrant evacuation, have sample counting instrumentation removed to RPDB.
(Ge-Li detector and dewer; NUCLEAR DATA 66 computer) 9.' The EMERGENCY COORDINATOR shall appoint and have a surveillance team check areas evacuated clear of personnel within 30 minutes.
NOTE: EMERGENCY DIRECTOR approval required for any voluntary radiation exposure in excess of 10CFR20 limits. (Up to 75 rem for ]-
i life saving, up to 25 rem to prevent exposures to members of general public in excess of 1 rem whole body and 5 rem thyroid.)
p
- 10. Determine the need for EMERGENCY SUPPORT ORGANIZATIONS and,if needed, activate them or place them on standby. See TABLE III, EMERGENCY SUPPORT ORGANIZATIONS.
Rev. 4/08/91 App'd \ Jay(T\
l r- . . - _ = , ~.__ - - , _ _ . . _.m_, . . - . . , m.. =., , _......,__y... . , . - - -
SEP-3 (Cont'd) Page 6 of 6 i
SUBSEOUENT ACTIONS:
- 1. Evaluate results of corrections and subsequent actions to determine need to escalate /de-escalate emergency classification.
- 2. Keep record of actions and evaluations for documentation. Use Procedures and worksheets.
- 3. Notify NRC, Region 111, that ALERT condition has occurred within one hour after event has been classified or reclassified. (Use Worksheet C)
- 4. Notify American Nuclear Insurers (ANI) [203-677-7305) that ALERT condition has occurred. (Use infonnation in Worksheet C) }
- 5. Notify';este Emergency Management Agency (SEMA) (314 751-2748] that ALERT tondition has occurred. (Use information in Worksheet C) ]
RECOVERY ACTIONS:
- 1. Evaluate potential radiological effects to onsite and offsite personnel before returning access to specific areas effected by ALERT emergency.
- 2. Procedures shall be written and approved for handling significant recovery evolutions.
NOTE: During recovery operations, personnel exposures to radiation should be maintained within 10CFR20 limits.
Rev. 4/08/91 App'd ()W\
l
SEP-4 (Cont'd) Page 2 of 6
- 15. Send operator to west tower with radiation monitor to:
NOTE: Communicate by intercom, since the stack monitor is affected by portable radio RF.
- a. Verify radiation background at stack monitor.
- b. Verify control room readings.
- c. Mark initial needle position on analog display with time for future analysis if control room display becomes inaccessible.
- d. Verify flow rate through monitor to 7 + 1 SCFM. If not, use Worksheet A to determine stack monitor values.
- 6. Pull stack monitor filters and analyze.
- 7. After determining radionuclide responsible and verifying concentrations greater than 95,000 M"C (a) secure EF-13 and EF-14; (b) secure RF2, SF2, RF1, SFl; (c) secure all individual vent fans.
- 8. The EMERGENCY COORDINATOR shall evaluate the need for a partial or total evacuation of the facility.
NOTE: For facility evacuations or northeast quadrant evacuation, have sample counting instrumentation removed to RPDB.
(Ge-Li detector and dewer; NUCLEAR DATA 66 computer)
- 9. The EMERGENCY COORDINATOR shall appoint and have a surveillance team check areas evacuated clear of personnel within 30 minutes.
NOTE: EMERGENCY DIRECTOR approval required for any voluntary radiation exposure in excess of 10CFR20 limits. (Up to 75 rem for lifesaving, up 1 to 25 rem to prevent exposure to members of general public in excess of 1 rem whole body and 5 rem thyroid.)
- 10. Determine the need for EMERGENCY SUPPORT ORGANIZATIONS and, if needed, activate them or place them on standby. See TABLE IV, EMERGENCY SUPPORT ORGANIZATIONS.
Rev. 4/08/91 App'd
. . - - . . . . - ~ . - . - - . . . . . - - . - . . .. ,
SEP-1 (Cont'd) Page 6 of 6 SUBSEOUENT ACTIONS:
- 1. Evaluate results of corrections and subsequent actions to determine need to escalate /de-escalate emergency classification.
- 2. Keep record of actions and evaluations for documentation. Use procedure and worksheets.
- 3. Notify NRC, Region Ill, that SITE AREA EhiERGENCY condition has occurred within one hour after the event has been classified or reclassified.
(Use Worksheet C)
- 4. Notify American Nuclear Insurers (ANI) [203-677-7305) that a SITE AREA EhfERGENCY has occurred. (Use information in Worksheet C) ]
- 5. Notify State Emergency hianagement Agency (SEhfA) [314-751-2748] that SITE AREA EhfERGENCY condition has occurred. (Use information in Worksheet C) ]
EECOVERY ACTIONS:
- 1. Evaluate potential radiological effects to onsite and offsite personnel before returning access to specific areas effected by the SITE AREA EhiERGENCY.
- 2. Procedures shall be written and approved for handling significant recovery evolutions.
T NOTE: During recovery operations, personnel exposures to radiation should be maintained within 10CFR20 limits.
Rev. 4/08/91 App'd M
SEP-7 (Cont'd)
Page 2 of 4
- 5. The MU News Bureau staff member contacted should veri',, , all concerning an emergency at the University of Missouri Research Reactc: oy 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 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.
After verifying the person's identity by asking for his social <ecurity number, the emergency call can be verified.
VERIFICATION LIST FOR MURR EMERGENCIES Name Soc. Sec. No- Name Eoc Sec. No.
Chuc}. Anderson Sue Langhorst Joe Baskett Charlie McKibben Rita Bonney Walt Meyer Kenneth Beamer Steve Morris Barry Bezenek Paul Muren ]
Joe DeMers Phil Neel Chester Edwards Leslie Powell John Ernst Mike Randolph Christine Errante Bill Reilly Mac Evans Tony Schoone les Foyto Jim Schuh John Fruits Tom Seeger Greg Gunn Vickie Spate Robert Hudson Ray Stevens Rolly Hultsch Nolan Tritschler Brenda Johnson Robert Walker Vernon Jones Mike Wallis Mike Kilfoil Tim Warner Ron Kitch
- 6. MU News Bureau personnel contacted will determine the need for staffing and equipping an emergency information center and will call in the required staff and arrange for necessary facilities.
- 7. MU News Bureau personnel will irdorm news media and others of the pubhc.
as necessary, of the emergency .
- 8. If possible, a MU News Bureau staff member will be sent on site to assist the EMERGENCY DIRECTOR with the release of information.
Rev. 4/08/91 App'd IMTM
Page 1 of 3 SEP-11 MONITORING PLANNED EXPOSURES IN EXCESS OF LIMTIS IN 10CFR20 NOTE: THE EMERGENCY DIRE ? TOR MUST APPROVE EACH VOLUNTEER TO EXCEED EXPOSURE LIMITS OF 10CFR20.
EURPOSE:
This procedure provides the guidelines for monitoring, dosimetry and records for persons who volunteer for life-saving and accident mitigatin t actMties which could result in planned radiation exposures in excess of 10 CFR 20 limits.
GUIDELINES:
A Emergency Exnosure Guidelines
- 1. A volunteer may be authorized to receive up to 75 Rem to save ]
human life.
2, A volunteer may be authorized to receive up to 25 Rem to prevent ]
radiation exposures to members of the general public in excess of the following Protection Act.on Guides (PAGs).
The Protective Actions for all classifications are based upon a PAG of 1 rem dose equivalent for whole body and 5 rem dose equivalent thyroid to members of the general public and MURR staff on site.
R Pfrsonnel Selection Considerations
- 1. Individual is a vol'unteer (preferably 45 years or older).
- 2. Individual is familiar with the radiological consequences of emergency radiatlon exposures.
- 3. Women of childbearing age shall not take part (Reg. Guide 8.13).
Rev. 4/08/91 App'd N p . _ _ .
EMERGENCY PROCEDU3E EMERGENCY CALL LIST
. . . HeaTILfhysics Operations Emerooney Sucocrt Orcanintiens
.EbonaR2 Eh00aDQ EbODRU2 S. Langhorst 442-3534 M. Evans 698-2450 1&iG Police 882-7201 R S. evens 442-2539 K. Beamer - 682-5499 J. Ernst 445-5621 R Kitch 696-3710 Columbia Eira Deoartment 9-911 J. DeMors 443-4938 C. Kribbs 682-3980 l
J. Schuh 874-3086 ] leiflotottaland C!inics ;
T. Seeger 875-8656 Emergency Services 882-6003 '
J. Baskett 474-2046 Ambulance 882-6128 cr 9-911
_DirDC1gis 02ce Walk-in (Emergency Center) 882-8091 EbQnRM2.
J. C. McKibbon 442-6728 UMGilaallh Physics (Ofree) 882-7221 Dr. Phil Lee (Home) 445-5275 Jamieson Shotts (Home) 474-2194 David Spate (Home) 657-9450 OpeIalj2ns Reactor Chemistry Ebcnang, Phone No. MU News Bureau 882-6211 W. A Meyer 442-7675 S Morris 445-4217 ] See Pubhc Information 882-6214 C. Edwards 443 7529 V. Spata 657-9450 Procedure for other or T.Schoons 443 8862 phone numbers. (SEP 7) 882-9142 R Hultsch 442-6653 State Ememency Macacement C. Anderson 696-5506 B.Bezenek 822.DGY (SEMA) 314-751-2748 445-5680 G Gunn 875-1162 NRC. Regien lil 708-790-5500 R Tritschler 474-9388 Amertcan hurleat insure, 203 677-7305 J Fruits 474-u774 R. liudson 875 0451 L V. Jones 445-2543 M. Kilfoil 449-2524 P- Muren 474-0979 ]
P. Neel 442-8693 M Randolph 474-0589 ]
R. )varmer 445-8077 M Wallis 443-8764 T. Warner 816-882-6740 Rev. 4/08/91 App'd _%h
WOIESHELT_C
- i coNrESTs or INnLucLLowt.'P EMERGIXCY_ESMGES TO niE NRc fu:G101n1 EL15th5YD NORMA 1, WORKING llOURS: ATTER llOURS/uT:rJasm: )
'7 rnlONAt uttn* OmcEir' "IIEADQUARTERS OIT. RAT 10NS OrnCER" l REGION til 706-7EO N& WASIIING1DN. D.C. 301-061-(650 ]
- 1. I'+tdk N.nr. tth ttb e rarik daar. ]
_ _ __ 1
,- 2. Im.tton of emergency event.
UNIVERStrY Or MISSOURI RESEARCil REACTOR ]
AT COLUMIllA. MISSOURI )
- 3. De6cription of emergency event and emergeAy class: }
h0TTrlCATION OF UNUSUAL EVr#r. ALERT. or SITE AREA EMERGENCY ]
i k
The cause of trdtlating event,if knowit.
]
- 4. raccard tkir evmt gierttti
_ )
- 5. Status of reactor e.g. abutdown, fuel damage. ]
- f. Was there actual release of radioactive rnaterial? (estirnate quantity) ]
1 lias the release been terminated?
]
- 7. What protective actions taken? c.g. evac tation of faellity, site area evacuation ]
8 What outside assistance is requbed? e.g. SEMA. Fire Department, Medical Facilities
]
- 9. Are there any injuries? Are the injured contaminated?
)
T
- 10. Estimate impact of release? e.g., is general public expected to te affected? )
FXIRCDC' DITECIOR-ALQ IOTWAllON TO Call Rv 4/03/91 A;p'd _W5M
FEP 1 (cont'd) Page 5 of 7 r^%
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EVACUATION ROUTES, RESE ARCH RE ACTOR FACILITY ricunt rte -
Rev, 4/08/91 App'd M, .
Page1ofI EEP3 EIEE_ERCEERW1E j
- 1. Any individual discovering fire shall notify reactor control (#13 or 2 5213 on ]
hall phones) of fire, giving nature and location of fire. The Shift Supervisor will activate the FACILITY EMERGENCY ORGANIZATION by page system and provide warning to stay clear of fire location.
t
- 2. SHIIT SUPERVISOR will call (9 911) to notify Columbia Fire Department.
- 3. EMERGENCY DIRECTOR will investigate the fire and determine steps to minimize hazard to both personnel and property.
NOTE: Assessment of offsite radiological consequences shall be determined.
This assessment may require escalating emergency response to a site emergency procedure (Unusual Event Alert).
- 4. The EMERGENCY DIRECTOR may contact the MU News Bureau to handle public information, if appropriate.
- 5. If the fire cannot be put out immediately with local fire extinguishers, the reactor WILL be shutdown to focus on fire.
- 6. Secure EF 13 and EF 14 if there is a potential for a fire spreading through ]
ventilation system. ]
- 7. Secure ventilation supply fan SF-1, north RTAll, South RTAH, at MCC-3 and ]
close all fire doors.
- 8. If the fire is in containment and cannot be immediately brought under control, initiate reactor isolation. If fire is in laboratory building and cannot be immediately brought under control, initiate Facility evacuation.
9.
The EMERGENCY COORDINATOR or EMERGENCY DIRECTOR should contact the Fire Department outside of the Facility and stay in contact with the INCIDENT COMMANDER to coordinate fire fighting and life saving efforts.
NOTE: The Fire Department INCIDENT COMMANDER coordinates all Fire Department / medical assistance personnel. The EMERGENCY DIRECTOR or his representative P ould meet the first fire truck on the scene outside of the Facility. The first ambulance at the emergency scene is designated for triage (sorting and allocation of treatment by injury priority) and will not provide transport for injured personne! ,
Rev. 4/08/91 App'd ,la/M
Page 1 of 1 FEP 3(a)
CONTROLROOhilESP.OESILIDALPLM Lt11!QlMIOJiX ElllE NOTE: Throughtout this procedure continue to monitor stack exhaust monitor, Alpha Laboratory exhaust monitor (ALPliA 6) or Alpha Laboratory room monitor (ALPHA 3) for indication of airborne radioactivity, as appropriate.
- 1. If a fire is detected by fire alarm or reported in the Alpha l2boratory, the shift supervisor (or senior licensed person in control) will call the Columbia Fire Department.
2.
The shift supervisor will activate the Facility Emergency Organization by page system and provide warning to stay clear of facility basement.
- 3. The Emergency Director will determine nature and specific location of fire (i.e.,if fire is in glove bo or equipment exterior to glove box).
- 4. If fire cannot be put out immediately with local fire extinguishers, the reactor will shut down to focus vtention on the fire.
5.
Ensure Alpha Laboratory doers are shut and personnel are out of the laboratory.
If no experimenter is present, cali the on call experimenter as soon as time permits. ,
- 6. Secure EF 13 and EF-14 at breaker on emergency distribution center only if 1 there is likelihood of fire spreading through ventilation system. ]
- 7. Secure ventilation supply fan SF-1, north RTAH, South RTAll, at MCC-3 1 and close all fire doors.
- 8. Secure electrical power to Alpha Laboratory at breaker 17 on 120/208V distribution center and breaker 2 on emergency distribution center.
NOTE: This will secure Alpha Laboratory supply and exhaust fans. .
- 9. Isolate Alpha Laboratory by closing supply and exhaust dampers, if possible.
- 10. The EMERGENCY DIRECTOR (or his delegate) should contact Fire Department outside of facility to provide specific information.
- 11. The EMERGENCY DIRECTOR will stay in contact with INCIDENT COMMANDER to cortdinate fire fighting and life saving efforts.
. z. Contact MU News flureau to handle release of public information.
Rev. 4/08/91 App'd bm
i l
I IllCAllrli PliYSICS STANDARD OPERATING )ROCEDUllES (New ninnual issued 10/29/00) [
t Section Page No. Revision No Revision Date ;
4 Preface 10/90 ,
IIP-18. 1, 2 3 1/12/01 I H P-37 1, 2 0 10/8/90 I IIP-38 1.2,3 0 10/8/00. i
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.. . :_..... . . . _ , _ - . ..___...._-....__.____.i..___ _ _ . _ _ ._.. _ _...._ _. _ ... . _ _ _ _ ___.
10 hiegawatt Standard Operating Procedures Volume 5 Health Physics .
Preface Theso Standard Operating Procedures are lasued as part of the radiation protection program for all operations performed at the University of !
hiissouri Columbia Research Renctor (h1LRRi Reactor Health Physics is ]
assigned radiation protection responsibilit for al. i u:.a*.,d activity at the j h1URR, and these procedures apply to eac. ap#cibis license as is -) i appropriate. ;
POLICY !
It is the policy of the MURR to prevent unwarranted radiation exposure to any person as a result of work performed at the facility. Work procedures ]
are planned to comply with applicable license limits for radiation exposure >
and to promote the concept of c oso being "as low as is reasonably achievable ]
(ALARA)." The words " reasonably achievable" are emphasized because ,
the research and development nature of the work at hiURR preclude total
]
avoidance of personnel radiation exposure.
I PURPOSE The purpose of these procedures is to_ provide guidance and to identify situations which require additional planning before work proceeds rather than provide specific protocols. The research and development nature of
-work at MURR precludes the development of specific protocols for all ]
situations. The procedures may specify that a specific protocol be provided
~ for certain operations.
RESPONSIBILITY TO OBSERVE THESE PROCEDURFJ ,
It is the responsibility of each person to observe these procedures as is appropriate and it is the responsi3ility of supervision and management to assure observance of them. If a situation arises for which necessary work ]
cannot be performed because of conflicting limitations in the SOP, the work should be performed under a Radiation Work Permit to assure adequate planning for radiation control. ;
Rev.10/90
-__ . _ . _ .: .. .. ._ ;. _ ~ _ . . ____ ._.a.-,. . 2._,
. . _ .. _ .._m _. m _ _ . _ _ _ _ -_ _ _ _ . _ . . .__ -
Rev. 3 _Page 1 o# * '
Appr'd b . k b _ u -- -
Date- 1/12/9 :
I calibration of Radiation Survey Instruments :
I Pollev Survey instru;ents used for personnel radiation monitoring i shall be caliteated traceable to NIST. ;
i II. Purpore The purpose of this procecure is to establish a standard method for calibrating radiation survey instruments.
III. Procedure ) ,
A. Precalibration j
- 1. Instrument should be contamination free. l
- 2. Replace batteries.
- 3. Allow instrument to warm up. )
'4. Adjust meter to zero.- -)
B. Reproducibility }- ,
1.- Expose instrument to radiation field three or more ]
times under identical conditions. ')
2.- -The readings should not vary from the-mean more )
than +/- 10%. ) ,
Calibration C.
Use a NIST traceable Cs-137 source with a characteri:ed ;
radiation field for the following steps. -Instrument readings should be within +/ -10% of known radiation values. Calibration-shall be performed. annually and after any= maintenance or adjustment other than battery ;
changes (Reference ANSI N323-1978). )
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SOP MP-19 Rev. 3 Page, 2 of 2 Appr'd I N ./ e - t-Date 1/12/F
- 1. Linear instruments )
- a. If controls are provided for each scale, check calibratJen at approximately 20% and 80% of full scale.
- 2. Logarithmic instruments )
- a. Calibrr.tlon should be checked at the midpoint of each decade.
- 3. Autoranging digital instruments )
- a. Check calibration at approximately 20% and 80%
of full scale on each of the operating ranges.
D. Instruments that cannot satisfy sections A., 3., and C. )
above should be tagged and removed from service. )
E. calibratien Recorde
should be filled out for each instrument.
Information necessary on this record includes:
- a. Date of calibration.
- b. Signature of calibrator,
- c. Calibration source used,
- d. Calibration output.
- e. Initial and final meter readings.
- 2. Label instrument with the folliwing information:
- a. Date of calibration.
- b. Initials of calibrator,
- c. Date next calibration is due.
- 3. Fecord calibration date and initials in HP instrument log.
_ __ _ _ _- _ __._ _ _ ~.~._.._ _ _ _ - _ _ - _ . _ . _...__
l SOP HP-37 Rev. O Page 1 of 2__
Appr'd N N. Ic h d Date. October O 1990 9.
l Experimenters Waste Disposal Procedure I. Policy Personnti using radioactive materials at MURR are responsible to minimize the amount of radioactive waste generated and to properly prepare waste for disposal.
II. Purpo?e The purpose of this procedure is to provide procedures for the segregation and preparation of radioactive waste prior to Health Physics pick-up and to provide assistance to prevent the generation of excessive waste. This SOP also serves to remind the experimenter that careful consideration is needed prior to irradiation or transfer of materials to the ability and cost tor disposal ~of all related. waste materials.
III. Procedure A. Insure all_ waste is dry.
B. Segregate all waste by isotope to the extent possible and by type.of material. Check to make sure that no ,
sLarp items are in the waste bags such as needles, glass, razor blades, etc. Waste should be segregated as follows:
- 1. Paper, plastics, rubber gloves and other compressible materials.
- 2. Needles, razor blades and extremely-sharp items placed into Lpproved "tupperware" type plastic container with lid.
- 3. Glass items.
4, Rabbit and hard plastic waste.
i SCP HP-37 Rev. O Page 2 of 2 Appr'd 8 M.Ia - Y Date Octcher O 1990 9,
C. Place waste.inside approved yellow plastic bag and label. Mark the bag with a Radioactive Waste tag and indicate the isotopes, activity amounts, generator name, date, room of origin and a brief description of the. ,
waste. Measure the dose rate of the waste and ensure all levels are less than 50 mR/hr at the surface of the bag. If dose rate is above this, contact H.P. for assistance.
D. Arrange for pick up with H.P.
IV. Any questions about unusual waste items or large bulky items should be directed to the Health Physics staff.
I r
1 I
i s
t
1 l
SOP HP-39 Rev. O Page 1 of 3 Appr'd N l v.M op}g
(
Date Octcher E 1090 Direct Barrel Compaction Operatien I. Purrere To provide instructions for the proper processing and compaction of dry low level radioactive waste, and to give instructions on the operation of the barrel compactor.
II. Equipment Barrel compactor Beta / gamma ion chamber survey instrument 15/16 in, socket and drive Rubber ended mallet Empty DOT approved Ba*rels Scale and calibrated meter stick Anti-spring back disks (optional)
Plastic liners III. Procedure A. Inspect cpen barrel to ensure it is free of defects (holes, weak spots, deformation, etc.). If barrel is found to be defective set aside and mark, do not use.
Ensure ventilation air flow to compactor.
B. Inspect waste to be compacted to ensure that it is free of excessive moisture and contains only dry compressible waste. If the waste does not meet the above criteria, set aside for drying or sorting.
C. If not using compacter disks, double line the inside of the drum with liners and drape the excess over the side of the barrel. Do not use liners with compactor disks.
Place approximately 2" of approved absorbent in the bottom of the barrel to absorb any succequent moisture.
Important: survey waste to be compacted to ensure that it is within approved disposal levels (200 mR/hr).
Also, periodically survey the barrel to ensure radiation levels do not exceed 200 mR/hr at the surface of the barrel.
SCP HP-39 Rev. O Page 2 of 3 Appr'd I eb u
(
8 51)90 Date October D. Raise compactor ram and insert barrel ensuring that it is properly oriented in compactor and centered under platen. Place waste into the compactor to fill barrel.
It is suggested that poly vial waste is put into barrel first to aid in compaction. As waste is placed into the barrel, make a list of the types of waste and the associated generators to be filled in on the Waste record form.
E. Once the barrel is full of loose non-compacted waste, shut lower compactor door and lower ram down to top of ,
barrel. Check to ensure that the platen is properly aligned with respect to the barrel. (Important :
Ensure that it does not touch the side of the barrel as it will crush the barrel and make it unusable!) Close upper door and lower ram to compact waste. Once fully extended leave ram at pressure for about two minutes to allow all air to escape.
F. If using anti-spring back devices open the upper door and check the level of the compacted waste at this point to see if additional waste can be placed below the roller hoop to be used. Once the waste is at this level -
raise ram and place disk on top being careful to center the platen on the di*k to ensure proper fit. Then lower ram and force the disk into the barrel and allow the disk to lock in at the roller hoop.
G. Repeat steps 6 and 7 above until the barrel is full of compacted waste. Caution, do not over fill as the barrel lid or the anti-spring back devices will not fit proporly.
H. Once full, properly seal the lid with the closure ring.
Assign the next waste number to the barrel and fill out the waste index and waste form. Mark the barrel with the assigned waste number.
SOP HP-39 ROV. 0 ._Page 3 of 3 Appr'd. IO
- i Date October A . (19)90 I. Weigh the barrel and record the weight on the barrel lid 1 and on the rad waste form. Measure the surface dose ;
rate on the barrel and record the maximum reading l (including the bottom) obtained on the waste cheet. !
Using the hottest spot on the surface of the barrel measure the radiation level at one meter and record the level on the waste form. Survey the barrel for loose i surface contamination by swipe method. Ensure that the i barrel is free of both alpha and beta contamination,
~
If not, decon the barrel, resurvey, and then record the- !
results of the survey.on the waste sheet. ,
J. Store barrel for future counting and analysis for -
isotopic content.
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M
1 SECTION 111 REVISIONS TO Tile IIAZAl(DS
SUMMARY
REPORT 1 July 1990 through 30 June 1991 IIAZARDS
SUMMARY
REPORT (original July 1.1965)
- 1. ORIGINAL llSR: Delete cristing section 7.1.3 in its entirety and replace with:
7.1.3 FUEL ELEMENT FAILURE DF'rECTION SYSTEM (P. 7-2)
A controlled amount of reactor primary water in the clean up system is bypassed around the demineralizer through a Tracerlab MWP 1 A Fission Products Water Monitor.
This system measures principally the fission product activity associated with 1-135 and contributions from 1 132,1-134, and 1-136. The system is on line continuously when the reactor is in operation. When out of service, the primary coolant is sampled at least once every four hours for evidence of fuel failure.
The ontput of the scintillation probe detector is fed into one channel of the Eberline Radiation Monitoring system (RMS 11). This signal is displayed on a analog meter that is equipped with an adjustable set point trip to alarm at a predetermined radiation level.
- 2. Delete cristing sections 9.7.1,0.7.2, and 9.7.4 in their entirety and replace with:
9.7.1 AREA RADIATION MONITORING SYSTEM (op. 9-20. 9-21)
The area radiation monitoring system monitors radiation at the locations and in the ranges as shown in Table 9.4. With the exception of the detectors located in the building exhaust air plenum, each detector is equipped with a high level alarm light.
111 - 1
TABLE 0.4 AREA RADINrlON MONITORING SYSTEM DINECTOR LOCATION DETECTION RANGE DEAM PORT FLOOR SOUTil WALL 0.1 10K mR/hr BEAM POlU FLOOR WEST WALL 0.1 10K mR/hr BEAM PORT FLOOR NORTli WALL 0.1 -10K mR/hr FUEL STORAGE VAULT 0.1 10K mR/hr BUILDING EXilAUST AIR PLENUM #1 0.1 -10K mR/hr BUILDING EX11AUST AIR PLENUM #2 0.1 -10K mR/hr REACTOR BRIDGE 0.1 -10K mR/hr NUCLEPORE FILTER 0.1 -10K mR/hr REACTOR DR1DGE ALARA 0.1 -100K mR/hr COOLING EQUIPMENT ROOM 0.1 -100K mR/hr The information from each of the remotely located detectors is displayed on pane. ters on the control room instrument panel. Each of the panel mm. is equipped with an adjustable alarm contact which illuminates a lamp at that meter and annunciates an alarm whenever the detected radiation level exceeds the set point.
Additionally, when the radiation level sensed by either of two building exhaust air plenum detectors or either of two reactor bridge monitors exceeds the trip level a " building isolation" is initiated, in a building isolation:
(1) The reactor is scrammed:
(2) The building is scaled (all ventilation opening are closed); and (3) the exhaust and supply fans are de energized.
9.7.2 FUEL RUltrURE MONITORING SYSTEM % 9-21)
The fuel rupture monitoring system monitors reactor coolant water for the presence of the fission product aethity. The method employed utilizes the technique of measuring the short-lived iodine isotopes. A scintillation detector measures the aethity deposited on an anion exchange resin column and subsequent electronic circuitry selects thr.t aethity due to radiolodine, 111 - 2 ,
A portion of the reactor cooiant bypass cleanup loop is taken off upstream of the demineralizer and passed through a filter, a cation column and an anion column. The scintillation detector views the anion column and senses any collected activity. Detector output is fed 'o a channel of the Eberline RMS 11, where the signal is prc, cessed. This information is indicated on a panel tueter that is equipped with an adjustable set point trip to alarm at a predetermined level.
D.7.4 SECONDARY COOLANT MONITORING SYSI)31 (P 9-221 A scintillation detector is installed in the return leg of the secondary piping. The output of the scintillation detector is fed to a channel of the Eberline RMS 11, where the signal is processed. This information is indicated on a panel meter that is equipped with a high level alarm.
REVISE FIGURE 9.3 OF SECTION 9
- 3. IISR ADDENDUM 1. SECTION 3.0 (p.17) and SECTION 3.21 (p.100)
Delete existing section 3.6 and 3.21 and replace with:
3.G DESCRIBE TIIE METHOD FOR INSURING REllUNDANCY IN DFTECTORS WHICH fNITIATE BUILDING ISOLATION Two independent detectors are used to initiate building isolation. One detector is located in the building exhaust air plenum on the fifth level of the reactor containment building, an one is located in the exhaust air stream form the reactor pool surface. These detectors are isolated from cath other in that the operation of one does not effect the operation of the other.
The AC line power supply to these two detector channels is common.
However, each channel develops its e n 'ow voltage supply which makes it independent of the other channel. Tne power supplies are monitored by an alann circuit which alerts the reactor operator in the event that power to any detector is lost. The resulting loss of signal will initiate a reactor isolation and scram. A lamp on the front of each channel indicates that power is available to the particular channel, i
Power to the area radiation monitoring system is from the emergency l bus so that in the event of loss of commercial power the area radiation j monitoring system is energized by the motor-generator set. The system l l
that initiates the building isolation on high radiation levels is either '
redundant or is provided with alarm monitoring circuits such that no single failure can result in the loss of isoladon protection.
3,21 " Describe the design used to assure that (1) the master trips for reactor isolation on high radiation level cannot be adjusted from the instrument panel, or (2) the meter setting cannot be turned off scale to make the trips inoperable.
The system which provides automatic reactor isolauon on high radiation level is an area radiation monitor of standard design and frequent nuclear industry applicadon. An isolation trip occurs when a count rate comparator which monitors the output of a particular detector senses a preset trip level. The preset trip level !s set by adjusting a potentiometer located behind the front cover plate of each channel.
Reactor operating procedures require that the reactor isolation trip settings be checked routinely as part of the startup checklist. In no case may a trip setung be deliberately changed, if the reactor is in operation, unless the change is authorized by the Reactor Manager.
The Eberline Radladon Monitoring System (RMS 11) is on the vertical console immediately in front of the reactor control console and in full view of the reactor operators, if a reactor isoladon trip setung was changed, the change would be observed and would have to be deliberate, since access to the trip setting potenuometer requires the use of screwdriver to reach through the front cover plate of each channel.
- 4. HSR, ADDENDUM 2 SECTION 3 (p. 9)
Delete Section 3 and replace with:
The Eberline RMS 11 has external access to the alarm and trip setting potendometers but this must be done using a screwdriver to reach through a front cover plate of each channel. No inadvertent or unmonitored change of set points is likely. The Eberline system uses voltage comparators to change the state of alarm relays for trip functions, instead of alarm contact arms used in the tracerlab ARMS.
111 - 4
- 5. HSR, ADDENDUM 2, SECTION 8 (pp 10,20)
Delete third and fourth paragraphs of Section 8 and replace with the following:
These " backup" isolation doors operate only in the event of radiation existing in the ventilation chambers of the east building tower. A remote indication and alarm is mounted in one channel of the Eberline RMS 11 radiation monitoring system in the control room.
The radiation detection system used employs a G M tube that has a dynamic range of 0.1 to 10.000 mR/ hour. in the event of instrument failure, loss of signal to the instrument channel will initiate a reactor isolation.
The independence of the backup isolation detector trip is achieveu by having its channel mounted in a separate rack unit from the primary building exhaust plenum trip unit. The design of the circuitry that initiates a Reactor Isolation (2KlA and 2KlB) will further provide independence between detectors.
Solenoid power which is taken form the commercial electrical supply.
is required to keep the backup isolation doors open. In the event of the failure of commercial power the doors will close and remain closed until power is restored. In the event of the loss of the compressed air supply the doors will be closed by gravity.
G. HSR ADDENDUM 4 SECTION A.3.3.11 Containment Building Isojation and Reactor Scram
. The Drst paragraph of this section should be deleted and replaced with the following:
The detectors for the building air plenum and pool surface high radiation scrams and containment isolation channels are powered by independent low voltage power supplies and are therefore not subject to single failure event. Although the power supplies receive AC power from a common source. loss of the AC power will automatically scram the reactor and isolate the containment bulkling due to the reactor isolation circuitry design.
111- 5
j l
A backup pleiturn exhaust detector and trip unk is incorporated in a separate rack unit front the priinary plenuin exhaust to provide a redundant plenutu sernin and isolation. All autontalleally inillated i reactor isolations will trip the backup doors and close the fifth level inotorized doors.-
- 7. FIGURE A.8 ARMS Delete Figure A.it ARMS and replace with revised figure.
Revistors of Figure A.8 was due to upgrade of ARMS Systern with the new Eberline RadiatJon Monitoring Systein (RMS 11). .
- 8. FIGURE 1.9 Model RM 12A Backup Door Control Current should bc ,
deleted.
- 9. Original Hazards Summary Section 3.
Bearn Hole Level Plan, Figure 3.1 Grade Level Plan. Figure 3.2 Delete Figure 3.1 and Figure 3.2 and replace with revised Figure 3.1 and Figure 3.2. ;
Revision of Figure 3.1 was due to converting a storage area into a i laboratory room for Transurantes material (Room 111A). Revision for Figure 3.2 is due to the addition of temporary office buildings to the west !
end of reactor facility. ?
- 10. Hazards Summary Report, Addendum 3 Figure 2.3, Electrical Distribution.
Replaec Figure 2.3 with revised Figure 2.T! Electrical Distribution. ,
Revision is due to' upgrading 120/208 distribution bus with 3 additional breakers.
- 11. Harmrds Summary Report, Addendum 3, Figure 2.2 Replace Figure 2.2 with revised Figure 2.2. - The revision is due to ;
replacement of and change oflocation of the pH and conductivity units.
~
The figure also shows the addition of a P-4 return line to the south side of cell 1. of the cooling tower.
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SECTION IV PLANT AND SYSTEM MODIFICATIONS 1 July 1990 tiv:ougli 30 June 1991 Modification 90 4: Alpha laboratory (TRilMPlj This modification document was created to rencet the conversion of a reactor storeroom to an ASha 1;1boratory which was constructed in the Facility insement. The construction included the installation of additional supply and exhaust fans and system liEPA filters. The supply and exhaust fans are used to maintain the proper pressure differential between the Alpha Laboratory and the remainder of the basement. This modification provides for an addittorial common alann panel installed in the control room to monitor important Alpha Laboratory parameters.
The safety evaluation for this modification docuntents that it does not present an unreviewed safety question as per 10CFR50.59.
Modification 90 2: P-4 Control Circuit This modification ensures that secondary cooling water is maintained at a sufficient rate to the air conditioning unit no matter what secondary cooling pump configuration is used for the reactor. The modification ensures, through a logic circuit, that whenever there are not two (2) secondary cooling pumps running. P-4 will run. P-4 is the pump designed to provide secondary cooling flows to the air conditioners in the absence of normal (two pump operation) secondary Dow.
The safety evaluation for this modification documents that it does not present an unreviewed safety questions as per 10CFR50.50.
Modification 90 3: Physical Steprity Enhancement This modification was completed to improve the facility security, based on a recommendation from an NRC safety study. Details of the modification are included in the security plan. The safety evaluation for this modification documents that it does not present an unreviewed safety question as per 10CFR50.59.
IV-1 l
Modification 881: Redirecting P-4 Dischtuge Flow to Southwest thiv of Cooling Tower This modification was installed to prevent the cooling tower from freezing up on maintenance days (when the reactor is shutdown), when there is a lower secondary coolant flow with only P-4 running. The secondary water flow and temperature through all three cells of the cooling tower, with P-4 running and the reactor shutdown, is insufficient to prevent the water front freezing on a normal winter day. This modification allows the secondary flow to be diverted to one half of one cell in the cooling tower.
This provides sufficient cooling of the secondary water for air conditioner operation and enough heat in one cell of the cooling tower to prevent freezing.
The safety evaluation for this modillcation documents that it does not present an unreviewed safety question as per 10CFR50.59.
Modification 88 4: Area Radiation Monitorinr1 System This modification documents the replacement of the original installation Tracer Lab Area Radiation Monitoring System (ARMS) with a new Eberline Radiation Monitoring (RMSill system. This modification also documents the removal of the original installation secondary coolant monitor (SCM) and fission product monitor (FPM) detectors and replacement with new detectors and control room readout. The new detectors utilize the same sample points as the old (SCM and FPM).
The safety evaluation for this modification documents that it does not present an unreviewed safety question as per 10CFR50.59.
Modification 88-10: Relocation of Y-6 Jumper Connection This modificat. ion eliminates the possibility of enetr' zing relay 2K12, with the pool isolation valve (valve 509) off of its open powlon. With this modification, the system operating design is not changed This design is intended to prevent pumping water to the pool from the pool system piping and components in the mechanical equipment room, via the pool clean up system with valve 509 shut, if this were to happen, the pool could overflow via the pool sweep system and flood the beamport storage ports on the beamport floor.
IV-2 i
The safety evaluation for this inodi!! cation documents that it does not present an unreviewed safety question as per 10CFR50.50.
Modification 901: Facility Evacuation llorns This modification was done to improve the facility evacuation system and extend the system to new specific locations, including the Temporary Office 13uildings (TOl3s) and the Alpha Laboratory. The evacuation system was changed by placing flashing lights in rooms and spaces where it was difficult to hear the evacuation horns.
The safety evaluation for this inodification documents that it does not present an unreviewed safety question as per 10CFR50.59.
Modification 912: Nitrocen Station Move to inner Hallway This modification document details the move of the Nitrogen station from the Reactor facility basement to the inr.cr passageway at grade level.
This inove was undertaken so that a welding station for radioactive cans could be located in the basement at the old nitrogen station location. The new location of the nitrogen system provides for better storage of full compressed gas bottles awaiting service.
The safety evaluation for this modification documents that it does not present an unreviewed safety question as per 10CFR50.59.
IV-3
SECTION V NEW TESTS AND EXPERIMENTS 1 July 1990 through 30 June 1991 New experimental programs during this period are as follows:
RUR 219. Request 115:
Experimenter: S.Gunn
Description:
This RUR authorizes the irradiation of Yttrium Oxide to provide research isotopes used in bone uptake studies in animals.
RUR 219, Request 117:
Experimenter: W. Yelon
Description:
This RUR audiorizes the irradiation of Chromium Oxide to provide a new type of source for the Compton Scattering experiment (Compton Canuna Spectrometer).
RUR 219. Request 119:
Experimenter: S.Gunn
Description:
This RUR authorizes Ole use of a Ixad Isothermal Calorimeter to measure ganuna heating at various locations in the graphite reDector.
RUR 219. Request 120:
Experimenter: G. L?hrhardt '
Description:
Thic RUR authorizes the irradiation of Praseodymium Chloride for the purpose of nuclear medicine research into radiotherapeutics.
RUR 219, Request 122:
Experimenter: S.Gunn
Description:
This RUR authorizcs the development and use of an epithermal neutron activation facility.
V-1
___-._-.__~m-.__._______m_._ _.._
RUR 228, Amendment:
Experimenter: W. Miller
Description:
This RUR Amendment authorizeo the testing and use of a new beam tube configuration for Beamport F.
RUR 278A:
Experimenter: S.Gunn
Description:
This RUR Amendment authorizes the irradiation of Lutetium Nitrate to provide isotopes for research testing and labelling antibodies for cancer studies.
RUR 284:
Experimenter: S. ' - n
Description:
T1 . (UR authorizes the irradiation of Selenium to ovide research isotopes for nutrition studies.
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, V-2
1 l
SECTION VI SPECIAL NUCLEAR MATERIAL ACTWITIES 1 July 1990 through 30 June 1991
(;
! 1. SNM Receipts: A total of 24 new fuel elements were received from Babcock and Wilcox (B & W), Lynchburg, Virginia.
. Grams Grams Shipper Elements U- R235 B&W MO315. MO316, MO317 MO318, 19,901 10,540 MO319 MO320, MO321, MO322, MO323 MO324. MO325, MO326.
MO327, MO328, MO329, MO330, MO331, MO332 MO333, MO334, MO335, MO336, MO337, MO338 2, No Spent fuel elements were shipped.
3, inspections: Physical security and Special Nuutar Material accountability inspections were conducted by the Nuclear Regulatory Commission (NRC), during the time period June 19-21, 1991. The MURR Special Nuclear Material Control Procedures were reviewed in December 1990 by the Procedures Review Subcommittee (of the Reactor Advisory Committee) as per the annual requirement.
4, SNM Inventory: As of 30 June 1991, MURR was financially responsible for the following DOE owned amounts:
Total U .= 66,163 grams Total U-235 =. 58,597 grams
. Included in these totals are 36 grams of U and 34 grams of U-235 non-fuel, DOE owned. In addition to these totals MURR owns 157 grams of U and 76 grams of U-235 All of this material is physically located at the MURR.
VI-1
The fuel elements on hand have accumulated die following burnups as of 30 June 1991:
Burned-un Elements Element No. MWD Element No. MWD Element No. MWD MO-232 145.46 MO-267 146.32 MO-289 146.92 MO-234 145.46 MO-268 149.81 MO-290 145.98 MO-239 145.05 MO-269 146.32 MO 291 146.92 MO-240 145.05- -MO-270 144.50 MO-292 147.45
- MO-241 146.30 MO-271 144.50 MO-293 146.30 MO-246 143.80 MO 272 142.75 MO-294 147.45 MO-247 146.78 MO-273 144.91 MO-295 149.31 MO-248 143.80 MO-274 148.75 MO-296 145.61 MO-249 146.78 MO-275 144.91 MO-297 149.31 MO-254 145.15 MO-276 148.04 MO-298 145.61 MO-255 126.70 MO-277 146.73 MO-299 147.24 MO-256 146.15 MO-278 148.04 MO-300 146.97 MO 257 126.70 MO-279 146.73 MO 301 147.24 MO 258 149.49 MO-280 146.34 MO-302 146.97 MO-259 135.40- MO-281 143.00 MO-303 149.76 -
MO-260 149.49 MO-282 146.34 MO-304 144.99 MO-261 135.40. MO-283 143.00 MO-305 149.76 MO-262 147.47 MO-284 148.85 MO-306 144.99 MO-263 135.36 MO-285 146.76 MO-307 146.33 MO-264 147.47- MO-286 148.85 MO-308 145.25 MO-265 135.36 MO-287 146.76 MO-309 146.33 MO-266 149.81 MO-288 145.98 MO-310 -145.25 Elements in Service MO-311 122.36 MO-321 0.00 MO-331 18. 7
MO-312 146.48. MO-322 0.00 MO-332 16.
MO-313 122.36 MO-323 72.70 MO-333 18.',s MO-314 146.48 MO-324 51.36 MO-334 16.78 MO-313 103.72 MO-325 72.70 MO-335 9.38 MO-316 - 88.94 MO-326 51.36 MO-336 9.05
- MO-317 103.72 MO-327 35.02 MO-337 9.38 MO-318 - 88.94. MO-328 19.79 MO-338 9.05 MO-319 83.01 MO-329 35.02
. MO-320 83.01 MO-330 19.79 Averag2 Burnup (all elements): 118.61 MWD VI-2
. . -- . .. - . _ . = . - _ . - _ _ _ _ - . . - - . - .-
SECTION Vil REACTOR PHYSICS ACTIVITIES 1 July 1990 through 30 June 1991
- 1. Fuel Utilization: During the period,1 July 1990 through 30 June 1991, the following elements reached licensed or feasible burnup and were retired:
Serial Number Final Core Date Last Used MWD '
MO241 90 39 08-13-90 146.30 MO288 90-52 11-12-90 145.98 MO289 90 36 07-23 90 146.92 MO290 90-52 11-12-90 145.98 MO291 90-36 07-23-90 146.92 MO292 90-52 11-12-90 147.45 MO293 90-39 08-13-90 146.30 MO294 90-52 11--12-90 147.45 MO295 90-57 12-10-90 149.31 MO296 90-46 09-01-90 145.61 MO297 90-57 12-10-90 149.31 MO298 90-46 09-01-90 145.61 MO299 91-06 02-11 91 147.24 MO300 91-02 01-21-91 146.97 MO301 91-06 02-11-91 147.24 MO302 91-02 01-21-91 146.97 MO303 91-14 04-01-91 148.04 M0304 91-11 03-11-91 144.99 MO305 91-14 04-01 149.76 MO306 91-11 03-11-91 144.99 MO307 91-18 04-29-91 146.33 MO309 91-18 04-29-91 146.33 Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial criticalities are obtained with four new elements or fewer as conditions dictate. A core designation consiss of eight fuel VII- l
. . .-= - . - _ . _ _ _ - - .. .-. . . - - = ..
elements of which only the initJal critical fuel element serial numbers are listed in the following table. To increase operating efficiency, fuel elements are used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number.
Fabrication Serial InitialCore Initial Core No, No. Load No. QDnatinc Date 55 MO311 90 37 07-23-90 55 MO312 90-42 08 27-90 55 MO313 90-37 07-23-90 55 MO314 90-42 08-27-90 55 MO315 90-45 09 17-9C-55 MO316 90-48 10-08-90 55 MO317 90-45 09-17-90 54 MO318 90 48 10-08-90 56 MO319 90-52 11-05-90 56 MO320 90-52 11-05-90 53 MO323 90-59 12 17-90 56 MO324 90-60 12-24-90 56 MO325 90-59 l'/ 17 90 56 MO326 90-60 12 , 90 57 MO327 91-09 02-18-91
- 57 MO328 91-10 02-25-91 57 MO329 9l-09 02-18-91
- 57 MO330 91-10 02-25-91 57 MO331 91-17 04-15-91 57- MO332 91-18 04-22-91 -
57 MO333 .91-17 04-15-91 57 MO334 91-18 04-22-91 58- MO335 91-25 06-10-91 58 MO337 91-25 06-10-91
- 2. Fuel Shipping: No spent fuel was shipped.
- 3. Fuel procurement: Babcock and Wilcox Lynchburg, Virginia, is MURR's fuel assembly fabricator. This work is contracted with the U.S.
Department of Energy and administered by EG&G Idaho inc., Idaho Falls, Idaho. As of 30 June 1991,139 fuel assemblies fabricated by Babcock and Wilcox had been received and 135 used in cores at 10 MW.
Vil-2 w a
- -. - = - . - - _.-. - - - - _ . . . -_- . .- .-
- 4. Licensing Activities: On August 1,1990, the Nuclear Regulatory Commission approved Amendment No. 20 to the Facility Operating License No, R-103. This amendment approves a new fuel design that allows the use of extended life aluminide fuel (EIAF) in the MURR. The new fuel design changes are made to decrease nuclear peaking and allow an increase in burnup which results in longer cycle times before fuel replacement. Consequently, the new fuel design should significantly reduce the fuel cycle cost and reduce the amount of U-235 needed per MWD of energy produced. This license amendment also modified the technical specifications associated with fuel design and use, On May 8,1991, the Nuclear Regulatory Commission approved Amendment No. 21 to the Facility Operaung License No R-103. This amendment temporarily increased the Special Nuclear Material Inventory under Facility License R-103 pending the establishment of capability for the offsite shipment of spent fuel. As part of its annual reporting require-ments, the status of establishing this spent fuel shipping capability is described below, On April 18,1990, MURR submitted a request to the Nuclear Regulatory Commission to amend the BMI-1 spent fuel shipping package Certificate of Compliance to authorize MURR to use this cask.
The Nuclear Regulatory Comtnission approved MURR as a user of the BMI-1 cask on Septemt er 27,1990 by Revision No.17 to Certificate of Compliance No.- 5957.
MURR staff proposed Fall 1990 shipments and then Spring 1991 shipments, but neither of the proposed shipments came about because of the unavailability of the BMI-1. The BMI-l cask is owned by Cintichem Corporation of Tuxedo. New York. Cintichem is in the process of de-commissioning their reactor and will not make the cask available until their own spent fuel is shipped off site. A DOE Environmental Assessment process has been holding up approval for Cintichem to ship spent fuel for over one year. An optimistic projection of when the BMI-1 cask may be available is late 1991/early 1992.
When MURR staff learned that the BMI-l cask would not be available for Fall 1990 shipments, other options were pursued.
VII-3
,s-+ em-- C 8-- -vM -ar-*'-
- 1) MURR and other University Research Reactors (URR) expressed concern to DOE officials about.the impact its Environmental Review process for approval to ship Cintichem fuel was having on spent fuel shipping capability for the URR community.
- 2) On January 23,1991, MURR staff discussed with the Nuclear Regulatory Commission Transportation Branch the possibility of getting a 10CFR71.7 Specific Exemption to ship spent fuel with the National Lead cask owned by the University of Missouri. This cask had previously provided years of safe and reliable shipments of spent fuel for the research reactor community before more recent QA requirements were established.
- 3) - On January 31,1991. MURR discussed with the Nuclear Regulatory Commission and General Electric the possibility of applying to use the GE-1600 cask to ship spent fuel.
The staff at MURR are continuing to pursue opuon 3 by performing the safety analysis required to make a submittal to the Nuclear Regulatory Commission for consideration of the GE-1600 package for shipping
. spent fuel.
A request for a unique purpose exemption as defined in 10CFR50.2 was submitted September 26,1986 and is pending.
- 5. - Reactor Characteristic Measurements:
Fifty-seven refueling evolutions were completed. An excess reactivity verification was performed for each refueling and the average excess reactMty was 1.82%. The largest excess reactivity was 2.67%. MURR Technical Specification 3.l(0 requires that the excess reactivity be less than 9.8%.
Reactivity measurements were pt. formed for 8 evolutions to verify reactivity parameters for the flux trap. Differential worth measurements were made on blades A, B. C. and D (twice). Total worth curves of blades A and D were measured. The primary coolant temperature coefficient, was verified by measurements.
Vll-4
. . - _ _ . _ _ _ .. _ _. . _ . .._- . _ - - _ _ _ _ . ~ ..... _.. _.~
Physical inspection of the following fuel element was performed to verify operational parameters.
MO-288 from Core 52 10/4/90 All measurements were within operational requirements.
]
VII-5
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SECTION Vill
SUMMARY
OF RADIOACTIVE EFFLUENT RELEASED TO TIIE ENVIRONMENT
- Sanitary Sewer Effluent 1 July 1990 through 30 Junc 1991 Descending Order of Activity Released for Isotope Totals > 1.00E-5Ci Nuclide Amount (Cl) Nuclide Amount (Cl) l H-3 1.GE-01 Eu- 154 1.1E-04 l As-77 1,1E-02 Rh-105 1.1E-04 I S-35 a lE-03 Ce-144 7.5E-05 Re- 186 2.3E-03 Sb-124 5.7E-05 Ca-45 1.5E-03 Gd-153 5.7E-05 Zn-65 9.1E-04 Br-82 5.lE 05 Se-75 9.lE-04 Ni-65 3.7E-05 W- 188 4.0E-04 Ir- 192 3.7E-05 Cu-64 3.6E-C4 Gd-159 3.1E-05 Co-60 3.5E-04 Eu-152m 2.5E-05 Cr-51 - 2.4E-04 Sc-46 2.4E-05 Cd-109 2.1E-04 Mo-99 1.6E-05 Eu-152 - 1,6E-04 Ba-140 1.5E-05 Rb-86 1.5E-04 Co-58 1.3E-05 Na-24 1.4E-04 Total H-3 1.6E-01 Total Other 2.5E-02 Vill-1
Stack Effluent 1 July 1990 through 30 June 1991 Ordered by % Technical Specification (TS) Limit Tot Release Average Isotope FY 90-91 Concentration TS Limit % TS*
(Cl) (uCi/ml) (x MPC)
Ar-41 5.2E+02 1.0E-06 350 7.500 1-131 1.2E-03 2.4E-12 1 2.371 H-3 1.5C+01 2,9E-08 350 0.042 Co-60 3 -05 7.2 E- 14 1 0.024 Ce-144 1.9E-05 3.7E- 14 1 0.019 Te-125m 3.8E-04 7.5E-13 1 0.019 I-135 3.1E-02 6.2E-11 350 0.018 1-133 1.2E-02 2.3E-11 350 0.016 Cd-109 1.4E-04 2.7E-13 1 0.014 Se-75 2.2E-04 4.3E- 13 1 0.011 1-134 1.lE 2.2E- 10 350 0.010 Cc-139 4.7E-06 9.3E-15 1 0.009 V-52 3.4E 01 6.8E- 10 350 0,006 I-132 2.6E-02 5.1 E- 1 1 350 0.005
.Cd-l15 1.8E-05 3.5E- 14 1 0.003 Cs-137 4.6E-06 9.2E- 15 1 0.002 Hg-203 ' 3.7E-05 7.3 E- 14 1 0.002 Ba-140 9.0E-06 1.8E- 14 1 0.002 Cl-38 2.2E-01 4.3E-10 350 0.002 Na-22 2.6E-06 5.2E-15 1 0.002 Tb-160 5.5E-06 1.1E-14 1 0.001 As-77 1.4E-02 2.7E-11 350 0.001 Cs-138 3.8E-02 7.6E- 11 350 0.001 Os- 191 2.6E-05 5.2 E- 14 1 0.001 Total 10.081
- Isotopes observed at <0.001% TS limit not listed.
Stack flow rate 3,3.700 ft.3/ min Vill-2
SECTION IX
SUMMARY
OF ENVIRON' MENTAL SURVEYS 1 July 1990 through 30 June 1991 Environmental samples are collected two times per year at eight locations (HP-ll: " Environmental Sampling") and analyzed for radioactivity.
These locations are shown in Figure 1. Soil and vegetation samples are taken at each location. Water samples are taken at three of the eight locations. Results of the samples are shown in the following tables.
- 1. Sampled during November 1990.
Detection Limthi*
Matrix Aloha Beta Gamma Tritium Water 1.0 pC1/1 2.6 pC1/1 210.6 pCl/l 24.6 pCi/ml of sample Soil 2 2 pCi/g 5.7 pCi/g 2.1 pCi/g N/A
-Vegetation 2.0 pC1/g" 2.7 pCi/g 3.2 pCi/g 24.6 pCi/ml of dk'illate Gamma and tritium analyses are based on wet weights while a'pha and beta are based on dry weights.
Detection limit for alpha emitters in vegetation samples is based upon ,
half of the actual sample mass. This was done to prevent an artificially low detection limit based upon a large sample mass. Calculations assume all alphas detected in vegetation samples came from one half of the actual sample mass. This was done to account for sample self attenuation.
IX-1
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rigure 1. MURR Environmental Program Sample Stations NOTE: September 1983 Cf ty sewerage plants at stations 8 and 9 closed. All waste water now processed at City Waste Treatment Faciifty at station 10.
Detennined Radionetivity Levels Vecetation Samples l
Sample Alpha Beta Gamma Tritium (nCl/c) (nCl/c) (pCl/c) (nC1/c) 1-V-38 < 2.0 16.6 < 3.2 < 24.6 2 -V -38 < 2.0 26.3 < 3.2 < 24.6 3-V-38 < 2.0 33.1 < 3.2 < 24.6 4-V-38 < 2.0 19.6 < 3.2 < 24.6 5-V-38 < 2.0 23.5 < 3.2 < 24.6 6-V-38 < 2.0 28.3 < 3.2 < 24.6 7-V-38 < 2.0 17.8 < 3.2 < 24.6 10-V-38 < 2.0 33.6 < 3.2 < 24.6 . _ _
Detennined Rr.dioactivity Levels Soll Samples Sample Alpha Beta Gammn (pct /c) (pCl/c) (pCl/a) 1-S-38 3.0 24.0 10.3 2-S-38 < 2.2 18.5 9.3 3-S-38 < 2.2 18.1 8.5 4-S-38 2.3 14.2 6.1 5-S-38 < 2.2 17.0 9.6 6-S-38 2.7 21.2 5.3 7-S-38 < 2.2 22.7 7.7 10-S-38 < 2.2 17.8 7.1 -
Determined Radioactivity Levels Water Samples Sample Alpha Beta Ganuna Tritium (pC1/1) (pCl/l) (pC1/11 (pCl/ mil 4-W-38 < l.0 18.0 < 210.6 < 24.6 6-W-3 8 < 1.0 13.5 < 210.6 < 24.6 10-W-38 < l.0 8.7 < 210.6 < 24.6 IX-3
- 2. Sampled during May 1991 Detection 1.imits*
Matrix Alpha Beta Gannna Tritium Water 1.0 pCi/l 1.5 pCi/l 28G.6 pC1/1 14.1 pC1/ml of sample Soil 1.0 pCi/g 1.5 pCl/g 1.6 pCl/g N/A Vegetation 1.9 pct /g 2.9 pCl/g 3.0 pCl/g 14.1 pCi/ml of distillate Ganuna and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
Determined RadioactNity 1,evels Vecetation Samples Sample Alpha Beta Ganuna Tritium (pct /c) (pCl/n) (pCl/c) 1pC1/c) 1-V-39 < l.9 39.9 < 3.0 < 14.1 2-V-39 < l.9 36.4 < 3.0 < 14.1 3-V 39 < 1.9 44.4 < 3.0 < 14.1 4-V-39 < l.9 48.0 < 3.0 < 14.1 5-V-39 < l.9 40.4 < 3.0 < 14.1 6-V-30 < l.9 51.2 < 3.0 < 14.1 7-V-39 < 1.9 37.8 < 3.0 < 14.1 10-V-39 < l.9 GS.7 < 3.0 < 14.1 IX--4
Detennined Radioactivity Levels Soil Samples Sample Alpha 13 eta Gamma incl /c) (nCl/c) incl /c) 1-S-39 1.3 23.0 < l.6 2-S-39 < l.0 16.4 3.4 3 S-39 < l .0 - 21.3 5.4 4-S-39 1.5 19.5 5.3 S-39 < 1.0 25.2 4.6 6 S-39 1.3 17.1 4.8 7-S-39 < l.0 25.7 5.8 10-S-39 1.6 21.9 6.7 Determined Radioactivity Levels Water Samples Sample Alpha Beta Gamma Tritium fpC1/11 inCi/1) (0C1/l) InCI/ml) 4-W-39 < 1.0 13.1 < 286.6 < 14.1 6-W-39 < l.0 9.4 < 286.6 < 14.1 10-W-39 < 1.0 14.6 < 286.6 < 14.1 IX-5
ENVIRONMENTAL TLDs The MURR llealth Physics staff have been working with Dr. R. Craig
- Yoder. Technology Manager with Landauer, Inc., to develop a TLD nionttoring program to monitor doses around the MURR Facility. Landauer has also been interested in establishing environmental monitoring services, and initial measurements for testing various combinations of TLDs and filters were started in April 1990. LIF and CaF TLDs were tried initially, but LIF has not proved reliable, so the currently deployed monitors now contain CaF and Al 023 TLDs. Since monitoring has been done on a quarterly basis, the testing process to find the best monitors has therefore been slow.
Monitor locations have also been identified and tested. Perimeter monitors located directly outside the MURR facility have been included in this TLD program. . Originally we located the perimeter monitors near the roof edge of the laboratory building to provide security. We felt this would also result in-a conservatively higher measurement, being located nearer the stack release point.with the major isotope released being Ar-41. The results from these roof TLD .nonitors have consistently been lower than the control monitors (negative net readings) and so the latest placement of the perimeter monitors have been made closer to the ground. All CaF TLDs ha*/e
- shrun doses to be less than 100 mrem per year. Dr, Yoder expects the resalts from the Al O23 TLDs to be more reliabic than those of the CaF TLDs, NUMBER OF FACILTIY RADIATION AND CONTAMINATION SURVEYS Surface Air Radiation . Contmination Samnles RWP 1989
- July 49 44 22 5 August 45 44 23 8 September 41 39 20 7 October 59 58 23 10 November 19 19. 22 2 December 59 59 21 4 1990 January 49 49 23 8 February 35 31 20 5 51 arch 47 44 21 1 April 52 53 22 4 May 28 26 23 G June M M 20 2 TOTALS 514 497 260 62 IX-6
Miscellaneous items In October 1990 Mr. James R. Schuh was hired into the MURR Health Physics Group as a Health Physicist. Mr. Schuh had been in charge of the MURR Reactor Chemistry Group and had been a part of that group for over four years. His dudes also included being the Quality Assurance Officer for the University's exempt release license (License No. 24-00513-36E).
Mr. Schuh is currently pursuing a Masters degree in Nuclear Engineering / Health Physics and has successfully completed Part I of the American Board of Health Physics Certificadon Exam. In February 1991, Mr.
John P. Ernst'was promoted from Health Physicist to Assistant Manager, Reactor Health Physics. In June 1991 Ms. Andrea Shipp was h! red into the MURR Health Physics Group as a Health Physics Technician Trainee. Ms.
Shipp has a BS in Biology and has 1.5 years experience as a Research Laboratory Technician in the MURR Reactor Chemistry and the Exempt Release QA Program. In addition to these indMduals named above, as of June 30,1991 the MURR Health Physics Group consisted of the Manager, one Senior Health Physics Technician, one Health Physics Technician, one Secretary, and two half-time Student Assistants, in October 1990, a complete reissue of the MURR Health Physics Standard Operating Procedures was made. This reissue of the HP SOPS was made in order to evaluate the assignment of controlled copies and to insure that these copies contained the up-to-date revisions of the SOPS. The majority of the HP SOPS remained unchanged and retained their existing revision number and issue date. The introduction to the HP SOPS was updated, one procedure was deleted, one procedure revised, and two new procedures were added, HP-7: " Response to Medi-Physics Hot Cell Gamma Alarm" was deleted since the process covered by this procedure is no longer
- being performed HP-18: " Calibration of Radiation Su vey Instruments" was modified to include description of calibration for more of the survey instruments used at MURR and to explicitly reference ANSI N323-1978, which has been used as the basis of the calibration criteria. HP-37:
" Experimenters Waste Disposal Procedure" to provide procedures for the segregation and preparation of radioactive waste by experimenters prior to pick-up by Health Physics. HP-38: " Direct Barrel Compaction Operation" was established to provide instructions for the proper processing and compaction of dry low level radioactive waste, and to give instructions on the operadon of the barrel compactor. Copies of the revised introduction, the revised procedure and the new procedures are attached at the end of this secuon.
ADCO Services. Inc. has continued to act as our institutional waste broker. Through ADCO, MURR disposed of 435 cubic feet of LSA material generated at MURR. In addluon. two dedicated waste shipments were made through Chem Nuclear to dispose of a total of 29.2 cubic feet of irradiated metal hardware (used beryllium reflector, graphite elements and miscellaneous activated reactor components), fission detectors, and irradiated samples and sample containers.
IX-7
__ _. . ._ ____m.._ _ _ . _ _ _ . _ . - _ . _ . _ _ . _ _ _ _ _ _ _ _
The program to improve ALARA review and documentation is continuing to be tested, modified, and improved in order to find the best fit-for ALARA review of the various working groups at MURR. The average
-monthly whole body deep doses in each group have typically been: minimal for Computer Development. Director's Office, Nuclear Engineering, and _
- Radiation Effects: 10 mrem for Facilities Management. Instrument Development, Nuclear Analysis Program. Neutron and Gamma Ray Scattering, and Radioisotope Applications: 20 mrem for Reactor Senices 50 mrem for Health Physics; and 90 mrem for Operations._ The challenge has been to choose the investigation levels initiating ALARA reports that are appropriate to review reasonable doses for individuals in these different groups and for subsets within these groups. The overall ALARA program remains strong. Due to the increase in demand for irradiation services over die past year, the number of samples irradiated at MURR has increased from the previous year by approximately a factor of 2.5, and die total activity of some of the major isotopes shipped have increased by factors ranging approximately from 1.2 to 2.9. Despite this increase in samples, the total person-rem for those indwiduals involved in handling these materials has remained nearly constant.
A new, updated 30 minute video was produced this year to include in the MURR Indoctrination Program which is required training for each person first obtaining unescorted access to the facility.
A new facility, the Alpha Laboratory. was put into use this year in the basement at MURR to support actinide research being conducted under University License Nos, 24-00513-32 and SNM-247. The MURR Health Physics Group has provided the radiation protection coverage and personnel training for this facility, and has increased the capability for alpha detection,
- monitoring and survey in support of this research program. In addition, funding was obtained from this program to install a barrel compactor for use in disposing of MURR radioactive waste. A portal monitor was also put into service during the past year to strengthen MURR's personnel monitoring capabiliues.
e IX-8
l SECTION X.
L i
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMEBTTERS AND VISITORS -
1 July 1990 through 30 June 1991 i
- 1. 'I;1rgest single exposure'and average exposure are expressed in millirem.
- 2. Minimal exposure is defined to be gamma <10 mrem; beta < 40 mrem; neutron < 20 mrem.
' 3 ME = Number of monthly units reported with minimal exposure.
- 4. AME = Number of monthly units reported with exposure above minimal.
, 5. AE = Average mrem reported for all units above minimal.
- 6. IIE = IIighest mrem reported for a single unit for the month.
- 7. Dosimetry services except for "Self Reading Dosimeters" are provided by R. S. Landauer, Jr. & Co.
Dosimeter Types: "C" - X. Gamma. Beta. Fast Neutron (Neutrak 144), 'lhermal Neutron: "G" - X.
Gamma. Beta: "U' -TLD (1 Chip Ring).
PERMANENTISSUE BADGES "C" Whole Body Badges (Deep Dose):
JUL -AUG SEP OCT NOV 'DEC JAN FEB MAR l APR MAY JUN ME -102 111 101 120 116 107 98 126 125 100 116 111 AME '59 45 55 46 53 58 65 46 38 66 51 52 AE 59 59 65 -76 69 68 69 74 80 67 73 58 II E 290 210 210 190 210 270 270 190 160 280 270 270 "G" Whole Body Badges (Deep Dose):
JUL AUG SEP OCT' NOV- DEC JAN FEB MAR APR MAY JUN ME 31 46 48 59 60 59 49 58 .
57 60 59 30 AME 5 6 3 4 3 1 7 5 3 3 4 44 AE 18 18 17 20 10 20 19 16 13 13 13 19 II E 50 30 20 30 10 20 30 20 20 20 20 '90 X-1
SECHON X t
SUMMARY
OF RADINGON EXPOSURES TO .
FACILITY STAFF. EXPERIMENTERS AND VISITORS 1 July 1993 through 30 June 1991 'I "U" TLD Finger Rings:
i
- ME 64 69 62 79 83 83 66 68 90 84 86 99 ;
AME-71 54 66 59 53 53 64 73 67 ~73 71 66 AE -174 199 178 217 198 231 231 229 207 190 254 200 HE 1350 '1080 1870 1080 920 860 '1600 2010 1210 880 4390 780 i Self Reading Dosimeters:
- i
)' JUL 'AUG SEP OCr - NOV DEC 'JAN- FEB MAR APR MAY- JUN l ME 10 10 15 3 2 11 10 6 4 11 10 '13 AME 61 -73 66 81 76 67 76 -79 84 '79 83 92
, AE 51 55 53 48 58 53 50 47 73 45 62 49 i
! II E 244 267 202 190 200 230 217 208 206 232 279 272 -
. SPARE ISSUE ilADGES a
"C" Whole Body Badges (Deep Dose):
l JUL AUG SEP OCF NOV DEC JAN FEB MAR APR MAY JUN j ME 48 69 56 52 74 61 48 56 56 '49 69 51 ;
AME 10 2 2 5 4 -6 10 2 2 9 5 7 ,
AE 57 105 15 20 58 44 41 50 65 17 34 13 II E 170 200 20 40 160 220 180 60 80 30 120 20 I X-2 -;
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