ML15107A018

University of Missouri, Research Reactor Center, Written Communication Technical Specification 6.1.h(2) Regarding a Deviation from Technical Specifications 3.2.a and 3.4.c

ML15107A018
Person / Time
Site:	University of Missouri-Columbia
Issue date:	04/15/2015
From:	Butler R A Univ of Missouri - Columbia
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15107A018 (6)

Text

UNIVERSITY of MISSOURIRESEARCH REACTOR CENTERApril 15, 2015U.S. Nuclear Regulatory CommissionATTN: Document Control DeskMail Station P1-37Washington, DC 20555-0001

SUBJECT:

Docket No. 50-186University of Missouri-Columbia Research ReactorLicense R- 103Written communication as required by University of MissouriResearch Reactor Technical Specification 6.1.h(2) regarding adeviation from Technical Specifications 3.2.a and 3.4.cThe attached document provides the University of Missouri-Columbia Research Reactor(MURR) Licensee Event Report (LER) for an event that occurred on March 21, 2015,that resulted in a deviation from MURR Technical Specifications 3.2.a and 3.4.c.If you have any questions regarding this report, please contact John L. Fruits, the facilityReactor Manager, at (573) 882-5319.Sincerely,Ralph A. Butler, P.E.DirectorRAB:jlbEnclosurexc: Reactor Advisory CommitteeReactor Safety SubcommitteeDr. Kenneth Dean, Deputy ProvostDr. Robert Hall, Associate Vice Chancellor for ResearchMr. Geoffrey Wertz, U.S. NRCMr. Johnny Eads, U.S. NRCUI1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: www.murr.missouri.eduFighting Cancer with Tomorrow's Technology AttachmentU.S. Nuclear Regulatory CommissionApril 15, 2015Licensee Event Report No. 15-01 -March 21, 2015University of Missouri Research ReactorIntroductionOn March 21, 2015, with the reactor operating at 10 MW in the automatic control mode, a"Channel 4, 5 or 6 Downscale" annunciation was received. This alarm is initiated when any oneof the three Nuclear Instrumentation (NI) Power Range Monitor (PRM) channels decrease belowa power level set point of 95%. All PRM channels indicated a decreasing reactor power level.All primary and pool coolant system pressure, temperature and flow indications were normal.Investigation revealed that the drive chain for the Rod Position Indication (RPI) encoder on theregulating blade drive mechanism had disengaged from the RPI encoder slave sprocket andbecame bound in the lead screw adapter drive sprocket. Upon discovery of this failure, thereactor was immediately shut down by manual scram and all action of reactor emergencyprocedures REP-2, "Manual Scram," and REP-7, "Rod Position Indication System Failure,"were completed. Failure of the regulating blade to be operable during reactor operation resultedin a deviation from Technical Specification (TS) 3.2.a, which states, "All control blades,including the regulating blade, shall be operable during reactor operation." Additionally, withthe regulating blade in an inoperable state, a deviation from TS 3.4.c had also occurred. TS 3.4.cspecifies that "The reactor shall not be operated unless the following rod run-in functions areoperable. Each of the rod run-in functions shall have 1/N logic where N is the number ofinstrument channels required for the corresponding mode of operation." This specificationrequires that the two rod run-in functions, < 10% withdrawn and bottomed, associated with theregulating blade must be operable when the reactor is in operation.Description of the Regulating Blade and Drive MechanismThe reactivity of the reactor is controlled by five neutron-absorbing control blades. Four of thecontrol blades, referred to as the shim blades, are used for coarse adjustments to the neutrondensity of the reactor core. The fifth control blade is the regulating blade. The low reactivityworth of this blade allows for very fine adjustments in the neutron density in order to maintainthe reactor at the desired power level.The regulating blade is constructed of stainless steel with an overall length of approximately 30-inches, occupying about 18' of the circular arc around the outer reactor pressure vessel. Theblade is driven at 40-inches per minute in both the inward and outward directions by itsassociated drive mechanism. The regulating blade drive mechanism consists of a servomotor, areduction gearbox, a lead screw assembly and an overload clutch. The lead screw assemblyPage 1 of 5 AttachmentU.S. Nuclear Regulatory CommissionApril 15, 2015converts the rotating motion of the servomotor to the linear motion of the regulating blade. Theoverload clutch allows slippage of the lead screw should the regulating blade become boundwithin the blade gap. The drive mechanism, through a slave sprocket and chain arrangement,also drives a RPI encoder transducer and a rotary limit switch assembly. The encoder transducerprovides an analog signal to the RPI chassis, which converts the analog signal to a digital readoutthat is displayed on the control room instrument panel and control console. The rotary limitswitch assembly actuates two regulating blade position alarm functions (20% and 60%withdrawn) and a rod run-in (< 10% withdrawn). A second rod run-in is initiated by a limitswitch, which is independent of the rotary limit switch assembly, when the regulating blade isfully inserted or "bottomed."The regulating blade may be operated from the control console in either one of two modes:manual or automatic. In the automatic control mode, the regulating blade controls reactor powerby comparing the output signal from the NI WRM with the setting of the power schedulepotentiometer as determined by the Reactor Operator. If a mismatch does exist, a positive ornegative output signal is generated and sent to the servomotor of the regulating blade drivemechanism, which repositions the regulating blade, stepwise, in a direction which minimizes thediscrepancy between the power schedule setting and the actual power level. Over the course ofthe week, while in the automatic control mode, the regulating blade frequently shims to makeminor adjustments to maintain power at the desired level.Detailed Event DescriptionAt 10:06 on March 21, 2015, with the reactor operating at 10 MW in the automatic control mode,a "Channel 4, 5 or 6 Downscale" annunciation was received. This alarm is initiated when anyone of the three NI PRM channels decrease below a power level set point of 95%. All PRMchannels indicated a decreasing reactor power level. All primary and pool coolant systempressure, temperature and flow indications were normal. No additional annunciations werereceived and no rod motion was in progress. The Lead Senior Reactor Operator (LSRO) directeda second operator to the reactor bridge to inspect conditions near the control and regulating bladedrive mechanisms. At 10:08, the operator discovered the drive chain for the regulating bladedrive mechanism RPI encoder had disengaged from the slave sprocket for the regulating bladerotary limit switch assembly and was bound in the drive sprocket preventing movement of theregulating blade in either the inward or outward direction. The LSRO immediately initiated amanual reactor scram and all actions of reactor emergency procedures REP-2, "Reactor Scram,"and REP-7, "Rod Position Indication System Failure" were completed. Failure of the regulatingblade to be operable resulted in a deviation from TS 3.2.a., which states "All control blades,including the regulating blade, shall be operable during reactor operation." Additionally, withthe regulating blade in an inoperable state, a deviation from TS 3.4.c had also occurred. TS 3.4.cPage 2 of 5 AttachmentU.S. Nuclear Regulatory CommissionApril 15, 2015specifies that "The reactor shall not be operated unless the following rod run-in functions areoperable. Each of the rod run-in functions shall have 1/N logic where N is the number ofinstrument channels required for the corresponding mode of operation." This specificationrequires that the two rod run-in functions, < 10% withdrawn and bottomed, associated with theregulating blade must be operable when the reactor is in operation.After the reactor was shut down and secured, the regulating blade drive mechanism was removedfor inspection and troubleshooting. It was determined that a sufficient minor misalignment hadoccurred over an extended period of time to allow the chain tension to vary slightly with therotational motion of the RPI encoder sprockets. This lack of a correct, consistent tensionallowed the drive chain to disengage from the RPI encoder sprocket.Safety AnalysisPreceding the failure, the reactor had been at continuous full power operation with the regulatingblade properly maintaining power level in the automatic control mode for a period of 88 hour0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br />sand 51 minutes since the last scheduled startup on March 16, 2015. The regulating blade hadbeen fully operational during that period. A review of the NI Wide Range Monitor (WRM) andPRM strip-chart recorders indicated an actual power level decrease starting about three minutesprior to receiving the "Channel 4, 5 or 6 Downscale" annunciator alarm; therefore, it appears thatthe regulating blade could have been inoperable for a period of approximately five minutesbefore the reactor was shut down.The regulating blade and its associated rod run-in features are not part of the reactor safetysystem as defined by TS 1.18, which states, "The safety system is that combination of sensingdevices, circuits, signal conditioning equipment electronic equipment and electro-mechanicaldevices that serves to effect a reactor scram, initiate a containment building isolation or activatethe primary coolant siphon break system." When a reactor scram or rod run-in occurs, theregulating blade is automatically shifted to manual control mode to prevent it from operating tomaintain power.The basis for the rod run-in features associated with the regulating blade is to assure terminationof a transient which, in automatic operation, is causing a rapid insertion of the regulating blade.The regulating blade < 10% withdrawn rod run-in is not required to prevent reaching a LimitingSafety System Setting (LSSS). The redundant regulating blade bottomed rod run-in wasoperable during the time the < 10% withdrawn rod run-in was inoperable.Page 3 of 5 AttachmentU.S. Nuclear Regulatory CommissionApril 15, 2015Corrective ActionThe reactor was shut down by manual scram when it was determined that the regulating bladewas inoperable. After the reactor was shut down and secured, the regulating blade drivemechanism was removed for inspection and repairs. A complete alignment was performed onthe chain drives and sprocket assemblies for the regulating blade RPI encoder, rotary limit switchassembly, regulating blade drive assembly, and idler arms. Chain tension was adjusted on alldrive chains after the alignments were completed. The shaft bushings supporting the RPIencoder sprockets were also replaced. The "Regulating Blade Operation And Rod Run-InFunction Test" portion of form FM-57, "Long Form Startup Checksheet," were completedsatisfactorily to verify proper operation of the regulating blade rotary limit switch assembly andregulating blade RPI.To prevent further failures of this type, more detailed instruction will be provided during theperformance of FM-57, "Long Form Startup Checksheet," as to the type of inspections required.This will ensure that a check of regulating blade chain tension is performed at least weekly.Additionally, this event has been entered into the MURR Corrective Action Program as CAPentry No. 15-0021, and any additional improvements or corrective actions will be considered.One of the possible long term corrective actions would be to relocate regulating blade rod run-infunctions directly to the drive mechanism lead screw assembly similar to that of the current limitswitches which provide the drive mechanism full-in and full-out stop functions. This wouldeliminate the need for a drive chain and the difficulties associated with aligning and providingthe correct tension for multiple drive chains, sprocket assemblies and idler arms on the samecomponent.If there are any questions regarding this LER, please contact me at (573) 882-5319. I declareunder penalty of perjury that the foregoing is true and correct.ENDORSEMENT:Sincerely, Reviewed and Approved,John L. Fruits Ralph A. Butler, P.E.Reactor Manager Director.A4 ~MARGEE P. STOUTMy Cwrission ExpiesMarch 24, 2016Page 4 of 5 AttachmentU.S. Nuclear Regulatory CommissionApril 15, 2015Regulating Blade Drive AssemblyRotary Limit SwitchSlave SprocketIII!RPI Encoder DriveChain (Disengaged)I LI__Regulating BladeIGearboxII Rotary Limit SwitchDrive ChainRPI EncoderSprocketsKI RPI Encoder DriveChain (Disengaged)I RPI EncoderPage 5 of 5