ML20117K826
| ML20117K826 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 04/30/1995 |
| From: | MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | |
| Shared Package | |
| ML20117K785 | List: |
| References | |
| FOIA-96-249 NUDOCS 9609120178 | |
| Download: ML20117K826 (3) | |
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1 FJLE UNIVERSITY OF MISSOURI RESEARCH REACTOR i
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OPERATIONS MONTHLY
SUMMARY
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April 1995 Prepared by:
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WALSH96-249 PDR g/g
April 1995 The reactor operated continuously in April with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdown.
On April 13, a manual rod run.in was initiated after receiving a fire main low pressure alarm and indication. A break was discovered in the water supply main from the nearby pumping station.
This water main supplies the emergency pool fill system 1,000 gpm capacity required by Technical Specification 3.10(c). The break was quickly isolated and sufficient water pressure was returned via alternate University wells. The reactor was refueled, and prior to commencing operation, an emergency pool fill compliance test procedure was completed satisfactorily. The broken main was repaired and water service was returned to its original configuration later in the week.
Major maintenance items for the month included: replacing the stack monitor motor, pulley, and belt; installing a new Gamma. Metrics wide range monitor detector in the reactor pool (separate from required nuclear instruments for preliminary testing); completing the biennial change-out of control blade offset mechanism "A".
UNSCHEDULED SHUTDOWNS l
l Date Number Tvoe Cause 4/13/95 1034 Manual Rod Run-In Fire main low pressure OPERATION
SUMMARY
HOURS OPERATED THIS PERIOD 647 TOTAL HOURS OPERATED 185,710 HOURS AT FULL POWER THIS PERIOD 644 TOTAL HOURS AT FULL POWER 184,739 INTEGRATED POWER THIS PERIOD 269 MWD TOTAL INTEGRATED POWER 71,122 MWD
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i MAINTENANCE ACTIVITY l
4/2/95 Replaced stack monitor motor.
4/3/95 Refueled - removed core 95-13, loaded core 95-14.
4/10/95 Refueled - removed core 95-14, loaded core 94-15.
l 4/13/95 Refueled - removed core 95-15, loaded core 95-16.
4/14/95 Replaced stack monitor motor pulley and belt.
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4/17/95 Refueled - removed core 95-16, loaded core 95-17; installed Gamma Metrics WRM detector for testing.
4/24/95 Refueled - removed core 95-17, loaded core 95-18; completed biennial change-out of control blade offset mechanism "A".
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Environmental Health & Safety 6
11 Research Park Development Bldg.
Columbia, Missouri 65211 UNIVERSITY OF MISSOURI-COLUMBIA Telephone (314) 882-7018 FAX [314)882=7940 Hazardous Waste Management 882-7018 April 14l 1995 Industrial Hygiene Services -
882-7018 Radiation Safety Office 882 7221 Workers' Compensation 882 7018 John B. Martin, Regional Admmistrator U.S. ' Nuclear Regulatory Commission Region ll!
801 Warrenville Road Lisle,IL 60632-4351 RE:
License No. 24-00513-32 Docket No. 030-02278 Response to Notice of Violation
Subject:
Monthly Progress Report of Safety Performance improvement Program -- Action Plan fi J.e University of Missouri-Columbia Radiation Safety Program
Dear Sir:
In accordance with commitments made by the University of Missouri-Columbia and with the NRC Order dated July 13,1994, this report is being submitted to you. The purpose of this report is to provide you with monthly progress on the completion status of the action items identified in the Safety Performance Improvement Program (dated June 20,1994). I have been providing you these monthly progress reports by the 15th of each month.
Enclosure I provides you with the completion status of the specific action items identified in the June 20, 1994 Safety Performance Improvement Program (University's Action Plan) that were completed in March 1995.
He University is committed to completing the specific action items within the time limitations, as stated in the University's Action Plan. It is our understanding that, by virtue of the NRC Order, we may make a written request of you to allow additional time to meet a step and provide the reason for the request and the new time frame for completion. He University has submitted a written request (dated February 15,1995) to change the frequency of submitting these progress reports to you. We understand that no change may be made without your written approval.
Sincerely, 7
40^^- k.
Susan M. Langhorst,
. D.,
HP Radiation Safety Office cc:
C.A. Kiesler, Chancellor B.J. Deaton, Chief of Stafr K.W. Groshong, Vice Chancellor J.K. Jones, Associate Vice Chancellor E. P. Sheridan, Provost J.P. McConnick, Vice Provost W.H. Miller, RSC Chair J.L. Beckett, Director s5 an eM opportunsfy snstifulcre n n Rhc'svn' O nn '
wo 2 4 1004 vi o v v va W ( C7 DTV
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Progress Report of the Safety Performance Improvement Program -
Action Plan for the University of Missouri-Columbia Radiation Safety Program Action Items Completed as of March 31,1995 l
PHASE THREE:
o Staffing needs will be specifically re-evaluated to assure that the program needs are being met. [Due~date -
March 31,1995]
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& annual review of the radiation safety program content and implementation will consist of two audits:
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& RSO will develop a %d.craive audit form to assum that all of the radiation safety records are reviewd each year and that discrepancies we identified; that conective actions are being initiated; that trends of noncompliance are noted; and program level corrective ac' tion prescribed.
[Due date - March 31,1995]
{ Completion - Comprehensive audit form was developed by March 31,1995. As part of the development cf this form, the Radiation Safety staffing needs were specifically re-evaluated and found to be meeting current program needs}
'e Ucense No. 24@513-32 Docket No. 030 o2278 4/14/95
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Research Reactor Center II Research Pat Coiumeia. M;ssom 65211 UNIVERSITY OF MISSOURI COLUMBIA h$g'ojg y April 19,1995 Directoc of Nuclear Reactor Regulation ATTN: Do:umentControlDesk Mail Station P1-37 U.S. Nuclear Regulatory Commission Washington. DC 20555
REFERENCE:
Docket No. 50-186 University of Missouri Research Reactor License R 103
SUBJECT:
Report as required by Technical Specification 6.1.h.(2) regarding reactor startup with the source range monitor in a degraded condition INTRODilCTION On March 20,1995, a reactor startup was commenced following a nonnally scheduled maintenance day.
The prerequisite Full Power Reactor Startup Checksheet had been completed, which includes a response test of the fission chamber detector for the source range channel to verify it is operable as required by Technical Specification 3A.a.
The staqup commenced at 2025, after taking the initial set of Nuclear Data and recording source range count rute to be used in the 1/M determination of critical rod height. Initial count rate was 900 cps and Estimated Critical Position (ECP) was 16.9 inches. The stanup procedure (SOP II.1.1) requires stopping rod back withdrawal in 5 inch increments until the rod bank is 2 mehes below ECP to take Nuclear Data.
At 2 inches telow ECP rods are pulled individually to establish criticality.
The stanup had proceeded to the point where the rods were withdrawn 10 inches. At this point, the startup was discontinued because the senior operator in charge of the startup saw no significant change in source range counts from those measured initially at zero inches. A review of reactor stanups for the past year indicates that, at 10 inches, source range count rate has typically increased 30 to SOE The reactor was shutdown by manual rod run.in at 2112 to investigate the lack of expected response.
Technical Specification 3A.a. requires the source range nuclear instrument to be operable only during reactor stanup. The inadequate response of the source range channel, noted by the reactor operator before temiincting the startup, indicates that the operability of the source range channel was questionable for the 47 minates the startup had progressed, even though it was response tested prior to stanup as required by the Ful. Power Stanup Checksheet and met the conditions of T.S. 3.4.e. which states-
"The reactor shall not be staned up unless the Source Range is indicating a neutron coant rat: of at least I cps and the Wide Range monitor is indicating a power level above I watt or the Source Range monitor is indicating a neutron test source of at least 2 cps and is verified just prior to stanup by a neutron test soun:e or movement of the monitor that the channelis responding to nCutrons."
E COLUMBIA KANSAS CITY ROLLA ST. LOUIS
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14ner to the Director of Nuclear Reactor Regulation April 19.1995 Page two Dfj.CRIPTION The source range nuclear instrument detector is a one inch diameter fission chamber with eight inches of sensitive length. The fissien chamber is mounted in a water tight container and is located in the pool outside the reflector region. It is connected to a mechanical drive system with 6 feet of stroke which allows vertical positioning o the detectorprior to startup. When not in use, the fission chamber is wi:hdrawn bro a boral therme.1 neutron shield to prevent excessive burnout of the chamber when the reactor is at power.
Technical Specification 3.4.a. requires the source range nuclearinstmment to be operable only during reactor stanup. When the reactor stanup was commenced on March 20,1995, the source range monitor had been response checked as specified in T.S. 3.4.e. and by Step 11 of the Full Power Startup Checksheet by driving the detector in towards the core and verifying increased count rate, and set to indicate greater than 1 count per second. The source range indicated 900 cps and the wide range monitor was rerdmg 750 watts, so the initial conditions of T.S. 3.4.e. were met.
The source range channel cppeared to be operable befcre reactor starrup, but was determinec..at to be responding adequately 47 minutes into the startup. The reactor was shutdown and the startup channel was again response tested by driving the movable fission chamber over the length of its travel to verify an increas:d response when closer to the source (beryllium reflector). The source ranj;e counts increased as the fiss on chamber was driven in, but did not decrease as expected when it was wnhdrawn. The count rate, compared to data from several previous startups, was considerably higher than norrnal at various fission :hamber heights.
Electronics technicians we.e called in to troubleshoot the difference in response. The source range drawer and preamplifier were checked and were determined to be operating normally. The fission chamber detector ar.d cables were removed for inspection and the cabling near the detector was brittle. The cabling from the fission chamber to the preamplifier was replaced and source range counts returned to the range logged for several previous startups.
A shori form precritical checksheet was performed, the source range monitor was response checked, and the reat tor w as started up without further incident.
ANA11_6M The discontinued startup had followed Standard Operating Procedure and, when commenced, met Technical Specifications 3.4.a. and 3.4.e., within the limits of the historical method used to verify operab lity. This method bad simply been to verify count rate increase on the source range channel as the fission chamber is inserted.
In retrcspect, this method (which had served us well for 27 years) will detect if the source range channel is not responding, but provides no guidance for determining whether the source range is over responding.
The main concern with over response is that gamma or noise background could obscure the neutron contribation to the count rate such that suberitical multiplication would not be observed.
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i Leuct to the Director of Nuclear Reactor Regulation Apn!19,1995 Page thx4 Review of previous startup records indicate that for normal stanups after maintenance day (12 to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> after shutdown), source range count rate is 100 cps or less for fission chamber height higher than 20 inches Jtom fullinserted. The source range de:ector is usually placed in the 20 to 25 inch range for startups after maintenance day. The count rate indicated for the March 20 sta-tup was 900 cps, which exceeded typical count rates and may have been caused by high noise background due :o detector cable insula: ion breakdown. Electmnics technicians checked the source range disenminatus circuits and elimir.r.ted them as a cause of the higher than normal response.
The source range channel is required by Technical Specification to be operable only during reactor startup It is not part of the reactor safety system, but provides improved monitoring cflow neuuun flux icvels at 4
startup to ensure that suberitica! multiplication and criticality can be observed during a startup. Safety Systerr.Pmtection from a Startup or Continuous Rod Withdrawal Accident (Itazards Summary Repoit, Addendum f. pp. 25-29)is provirled by the period scrams associated with the two intermediate range l
instruments, which were operable.
During the March 20 startup, the wide range monitor, which also monitors reactor power level down to source range level. was operaP nnd indicating 750 watts. This indication is well above the nwatt thresheld stated in T.S. 3.4.e. and was capable ofindicating criticality if the startup had proceeded further than 10 inches of rod withdrawal (6.9 inches below ECP).
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('ORRICIIVE ACTION The irrnw.inte corrective action was a reactor shutdown taken by the console operator when source range count rate did not change as expected with the rods withdrawn to 10 inches.
Review of the technique for response checking the source range channelindicated that no limit had ever been establir.hed for considering the murce range operability degraded when higher than nonnal response i
is indicated. This has been corrected by a Standing Order to Reactor Operations staff providing a range of expectsd values for source range counts based on time after shutdown. Count rates higher or lower than the expected range require investigation by electronics technicians before startup can commence. This evalcadon will be in addition to the current response check of the source range channel and will be added i
to the Full Power Stanup Checksheet at the next revision of Standard Operating Procedures.
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- Sincersy, ENDORSENENT:
q Reviewed a Appmved a
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Walt /.. Meyer Jr.
J. Charles McKibben g
Reacter Manager Associate Director xc: Mr. Alexander Adams. Jr., USNRC Regional Admir.istrator, NRC, Region III Dr. Jonn P. McCormick, Interim Vice Provost for Research and Graduate School Dean, UMC Reactor Advisory Conuni: tee
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Reactor Safety Subcomrmttee Maryenn w eemson PuosesueofM0 Commasen Eg
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