ML080440386

301 SRO Written Exam with Kas, References, & Answers

ML080440386
Person / Time
Site:	Sequoyah
Issue date:	02/08/2008
From:	- No Known Affiliation
To:	NRC/RGN-II
References
Download: ML080440386 (256)

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f-\-llb 4-N.SLu e12-S 1/2008SequoyahSRONRCExam 02108120081.Giventhe followingplantconditions:-Unit1trippedfrom10

%powerduetotripofbothMFPTs.-TheAFWpumpsstartsignalwasgeneratedfromthetripofbothMFPTs.-Steam generatorlevelsdroppedto 12%(LowestLevel)posttrip,andareslowly rising.Which.ONE(1)ofthefollowing describes the operatorresponsetoenablethe operator to MANUALLYcontrolAFWflow?

A':IMOAFWLCVsmustbetakentoAccidentResetbeforethevalvescanbe controlled manually.NOresetisrequiredtocontrolTOAFWLCVsmanually.B.TOAFWPumpmustbetakentoAccidentResetbeforetheassociatedAFWflowcanbe controlled manually.NOresetisrequiredtocontrolMOAFWLCVsmanually.C.BoththeTOAFWPumpandtheMOAFWLCVsmustbetakento Accident ResetbeforeAFWflowcanbecontrolled.

O.NeithertheTOAFWPumpnortheMOAFWLCVsmustbetakento Accident ResetbeforeAFWflowcanbecontrolled.Page1 1/2008 SequoyahSRONRCExam 02/08/2008A.Correct;The MO pump LCVs must be resetandwhiletheTO AFW pump must be reset in order to control the speed oftheturbine,theLCVsrequireno reset action.B.Incorrect;TheTOLCVsdo notrequirethe accident reset and the MO AFW LCVsdorequirethereset.Plausible becausethecandidatecouldconfusetheTO AFW pump reset action requiredwiththe MO AFW LCVs.C.Incorrect;TheTOLCVsdo notrequirethe accident reset and the MO AFW LCVsdorequirethereset.Plausible because the candidate could correctly determinethatthe startfromthetrip ofbothMFPisan accident signal that requiresthereset, butconfusethe reset oftheTO AFW speed controlwiththe reset ofthevalves and concludethatboth hadtobereset.

O.Incorrect;TheTOLCVsdo notrequirethe accident reset and the MO AFW LCVsdorequirethereset.Plausible because the candidatecouldthink thatsincethe low level start signalwasnot reached no accident signal was generated andconcludethat neither would nothavetobereset.Page2 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.1KIA:007 EA1.08 Ability to operate and monitor the followingasthey applytoa reactor trip:AFWSystemTier1Group1 Importance Rating: 4.4/4.3 Technical

Reference:

ES-0.1 Reactor Trip ResponseEA-3.8,ManualControlofAFWFlow Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPL271EA-0.1 8.6 Question Source: Bank#-----ModifiedBank

1. -----NewX--QuestionHistory:NewforSQNNRCExam 1/2008 Question Cognitive Level: Analysis10CFRPart55 Content: 41.5/41.10/45.6/45.13 Comments:Page3 1/2008 SequoyahSRONRCExam 02/08/2008 2.Given the following:

Unit 1 Reactor Trip ISafety Injection initiated duetoa pressurizer relief valve being stuck partially open.Reactor CoolantPumpshavebeen stopped.Pressurizerlevelis 60%and slowly rising.RCS pressureis1310psigand stable.Core Exit Thermocouple temperatureis580°F.What wouldbethe effect on Reactor VesselLeveland PressurizerLeveliftheRCS pressure is lowereddueto increased pressurizer relief valve leakage?Reactor Vessel Pressurizer Level Level A.Rising Continuetoriseatthesamerate B.Rising Rising faster C.Dropping ContinuetoriseatthesamerateDropping Rising fasterPage4 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,withtheRCS pressure and temperaturegivenatsaturation, a steambubblewouldbe formedinthe reactor head if RCS pressurewerelowered.Thiswouldcausethewater levelinthevesseltodrop instead of rise as statedinthe distractor and the pressurizer leveltoriseat afasterrateduetothe expansion of thesteamvoidforcing waterintothepressurizer.Plausible if student does not recognize saturated conditionsinRCSand effect ofbubblegrowthon Pressurizer level.B.Incorrect,withtheRCS pressure and temperaturegivenatsaturation, a steam bubblewouldbe formedinthe reactor head if RCS pressurewerelowered.Thiswouldcausethewater levelinthevesseltodrop instead of rise as statedinthedistractor.Plausible if studentdoesnotrecognize saturated conditions in ReS and effect ofbubblegrowthon Pressurizer level.C.Incorrect,withtheRCS pressure and temperaturegivenatsaturation, a steambubblewouldbe formedinthe reactor head if RCS pressurewerelowered.Thiswouldcausethewater levelinthevesseltodrop as statedinthedistractor.

However the response of the pressurizerwouldbetoriseat afasterrateduetotheexpansion ofthesteamvoidforcing waterintothepressurizer.

Plausible if student doesrecognizevoidformationin headanddoes not know effect of bubblegrowthon Pressurizer level.D.Correct,withtheRCS pressure and temperaturegivenatsaturation, asteambubblewouldbe formedinthe reactor head if RCS pressurewerelowered.Thiswouldcausethewaterlevelinthe vesseltodrop as statedinthe answer and the pressurizer leveltoriseat eiesterrateduetothe expansion ofthesteamvoidforcingwaterintothe pressurizer.Page5 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.2 Tier_1_Group_1_KIAAPE008 AA2.29 PZR Vapor Space Accident: Ability to determine and interpret the followingasthey apply to pressurizer Vapor Space Accident: The effects of bubble in reactor vessel Importance Rating: Technical

Reference:

3.9I4.2ES-1.2,PostLOCA Cooldown and Depressurization Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPL271ES-1.2 8.4 x Question Source: Bank#-----ModifiedBank#

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New-----Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge__--:--__Comprehension or Analysis X10CFRPart55 Content: Comments: 43.5 145.13Page6 1/2008 SequoyahSRONRCExam 02/08/20083.Unit1 Reactorhasbeen tripped with plant status as follows: RCS pressureis1325psigand slowly dropping.RCS temperature is 530°Fandstable.

Pressurizerlevelis 17%and slowly dropping.Containment pressureis2.1psigand slowly rising.SG pressures are-1005psigandstable.

SG levels are-40%andstable.

-Annunciator TS-62-43 REAC COOLPMPSSEAL WATER TEMPHIGHisLITand indicatorforRCP#3reads 227°F and steady.-Annunciator TS-62-42 REAC COOL PMPS LOWER BEARING TEMPHIGHislitand indicatorforRCP#1reads 201°Fandsteady.

Which ONE (1)ofthe followingisthe correct action for the RCP(s)in these conditions?A.AllRCPs arerequiredtobe tripped.B.ONLYRCP#1is requiredtobe tripped.ONLYRCP#3is requiredtobe tripped.D.ONLY RCPs#1and#3are requiredtobe tripped.A.Incorrect.

RCPstripcriteriais1250psig and the pressureisabovethesetpoint.

Plausible becausethereis a low pressuretripcriteriathathasnotbeenreached.

B.Incorrect.

RepstripcriteriaiswhenPhase B actuates at 2.81psigandthe pressure is belowthePhase Bsetpoint.Plausible becausethereis a high-high containment pressuretripthatifthe setpoint is reachedwouldrequiretrippingtheRCPs.

C.Correct.RCPsealcondition requiringtripis225 0F, and the stated seal temperatureisabovethisvalue.D.Incorrect.TheRCP Lower Bearing temperature is below the temperature(225 0F)requiringtheRCPtobetripped.Plausible becausethereis a setpointforthe Lower Bearing temperature requiring the affectRCPbetripped.Additionally,the Lower Motor bearing temperature trip setpointis200 0F and the lower pump bearing temperature could be confusedwiththe lower motor bearing.Page7 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.3 Tier_1_Group_1_KIA EPE009 EA2.24 Small Break LOCA:Abilitytodetermineor interpretthefollowingastheyapplytoa smallbreakLOCA,RCP Temperature Setpoints Importance Rating: Technical

Reference:

2.6I2.9E-1Lossof Reactor or Secondary Coolant AOP-R.04ReactorCoolantPump Malfunctions AnnunciatorResponce1-AR-M5-B(E-2)and(E-4)

Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.RCP B.5.c OPL271 AOP-R.04 x Question Source: Bank#-----ModifiedBank#

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New-----Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge_ComprehensionorAnalysis

_X_10CFRPart55Content:

Comments:CFR43.5 I 45.13Page8 1/2008SequoyahSRONRCExam 02/08/20084.E-1,Lossof Reactor or Secondary Coolant, directs the operatortoperforma transfertoHotLeg Recirculation.

WhichONE(1)ofthefollowingstatements correctly describesthebasisforthis realignment?

A.RealignstheECCSflowtoreduceCoreExit Thermocouple temperature to acceptable values.B.RealignstheECCSflowtocoolthereactorvessel upper internals package.C.RealignstheECCSflowtopassthroughtheRHRheat exchangerstoremovedecayheat.RealignstheECCSflowtopreventboron precipitation.A.Incorrect;PlausibleduetoHotlegcoolingwill putcoolwatertotheregion of theGETsthuscoolingtheGETs howeverthisis notthebasisfordoingso.

B.Incorrect;The transfertohotlegrecircdoes putflowontop ofthecorebutnottocoolthe upperinternals.Plausibleduetoaligningtheflowtothecore outlet and reversingflowthe knowledge ofknownflowpathsincorespecifictocoolingupper internals.

G.Incorrect;WhiletheGGPandSIPEGGSflowwhen suppliedfromthe RWST does not go through any heatexchanger,theRHRflowisalways alignedthroughthe RHR heat exchangersandwhenthe transfertothe containmentsumpisinitiatedthecoolingflowis placedontheRHR heat exchangerstocoolthewatercomingfromthe containmentsump.Plausibleif confusedinthe alignment ofthecoolingflow,withthe alignment offlowthroughtheRHR heat exchangers.D.Gorrect;EPM-3-E-1statesEGGSflowis realignedtoreverseflowthroughthecore to address the consequences of boron stratification/plate out.Page9 1/2008 SequoyahSRONRCExam 02/08/2008 Question No.4 Tier_1_Group_1_KIAEPE011EK3.13LargeBreakLOCA,Knowledgeofthereasonsforthe followingresponsesastheyapplytotheLargeBreakLOCA:Hot-Leginjection recirculation.ImportanceRating:3.8I4.2 Technical

Reference:

E-1,LossofReactororSecondaryCoolant,Rev23EPM-3-E-1,BasisDocument,ForE-1,Rev5 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:OPL271E-1B.4QuestionSource:

Bank#_X_ModifiedBank

1. _New-----QuestionHistory:SQNNRCEXAM 1/2008,SONBankquestionE-1-B.4003 QuestionCognitiveLevel:Memoryor fundamental knowledge X ComprehensionorAnalysis

_10CFRPart55 Content:(CFR41.5 141,.10 145.6 145.13)Comments:Thewords"step23"wasremovedfromstem.corrected answerwordingchanging from'RealignstheEGGSflowtoreverseflowthroughthecoreto address the consequences of boron stratification/plate out'to'RealignstheEGGSflowto reverseflowthroughthecoreto prevent the consequences of boron precipitation.

'Page10 1/2008SequoyahSRONRCExam 02/08/20085.Unit ,1 is operatingatfullpower.Giventhe followingeventsand conditionsonthe RCPs: Alarms indicatealossof ALLCCSflowtotheRCPs.

Seal injectionflowratetoeachRCPis8gpm.WhichONE(1)ofthefollowing identifieshowthe operationoftheRCP'swillbeaffectedifthe operatorsdonotrespondtothisalarm?A.TheRCPsshould operate without CCS indefinitely.B.TheRCPswill experiencesealfailure,C.TheRCP stator windingswilloverheat.TheRCPmotor bearingswilloverheat.A.Incorrect,theRCPscannotoperatewithout componentcoolingwaterbecausethe motor bearingswilloverheat.Plausibletoconcludethatduetothesealinjectionflow,the loss of thermal barriercoolingwouldnotbeanissue.B.Incorrect,TheRCPswill NOTexperiencesealfailure as long assealinjectionflowispresent, but plausiblebecausesealdamagewould occur iftheCCSwerelostandsealflow was not present.C.Incorrect,TheRCP statorwindingsarenotcoolingbyCCS.The motorcoolersuse ERCWtocooltheairleavingtheRCPmotors.Plausible iftheRCP motorcoolingis confusedwiththeRCP motor bearing cooling.D.Correct, Loss ofcoolingtothe motor bearingswillceuse overheating of the motor bearings anddamagetotheRCPmotor.Page11 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.5 Tier_1_Group_1_KIA 015/017 AK2.08RCPMalfunctions,Knowledgeofthe interrelationsbetweenthe Reactor Coolant Pump Malfunctionandthefollowing,CCWS.

ImportanceRating:2.6I2.6 Technical

Reference:

AOP-M.03 AOP-R.04FSAR5.5.1.2 1-47W859-2 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPL271AOP-M.03 B.6 OPT200.RCP B.4QuestionSource:

Bank#_X_ModifiedBank#

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New-----QuestionHistory:SQNNRCEXAM 1/2008,SEQBank AOP-M.03-B.4 8QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysisX10CFRPart55Content:(CFR41.7 145.7)Comments:Page12 1/2008SequoyahSRONRCExam 02/08/20086.Giventhe following plant conditions:

Reactorpoweris steady-stateat75%.PressurizerLevelControl Selector Switch (XS-68-339E)isinthe339/335position,andlevelcontrolisinautomatic.

Temperatureinputtothe pressurizerlevelcontrolsystemfailsto530°F.

WhichONE(1)ofthefollowing describestheeffectthis conditionwouldhaveonthe pressurizerlevelcontrolsystem?(Assume NO operator action)A.Charging initially increasesto120gpmthenreturnstonormaland pressurizer level stabilizesata higher value.Charging initially decreasestominimumflowand indicated pressurizerlevellowers towhereit stabilizes.

C.Charging decreasestominimumand indicated pressurizerlevellowersto17%,thenlevelrisestothehighlevel reactortripsetpoint.

D.Charging increasesto120gpmandthe pressurizerlevelrisestothehighlevel reactortripsetpoint.Page13 1/2008 Sequoyah SRO NRC Exam 02/08/2008 The controllerusesTavgastheinputforfor levelsetpoint.The programed level ramps from24.7 to 60%asTavg changes from 547-578 degrees F.If the controller setpointinput(Tavg)failedto a value of 530 degreesF,then the controller wouldsensethe levelashighand start reducing the chargingflowto lowerlevel.The controller has aminimumcapat24.7%whichis where levelwouldbeat 547 degrees F.A.Incorrect, Charging would notincrease(as explainedabove)Plausible if candidate confuseswhichwaythechargingflowwouldbe affected by the failure and/or because otherfailureswouldcause chargingflowtoincrease.

Level setpointfailinghighwould resultinthisscenario.

B.Correct,the temperatureinputfailure resultsinthe pressurizer level setpointtodropto 24.7%.Theinitial levelwouldbe60%, therefore the control system would decrease charging to lower the levelfrom60%tothe 24.7%setpoint.C.Incorrect, Levelwouldstabilizeat24.7%as explainedinabove.Plausible because otherfailureswouldcauseleveltodropuntil letdownisolatesat 17%, then pressurizer refills andtriponHigh level occurs.Controlling channelfailinghighwould resultinthisscenario.D.Incorrect, charging does notincreaseas explainedin'B'above.Plausible because otherfailureswouldcauseleveltoincreaseuntil pressurizer fillsandtriponHigh level occurs.Controlling channelfailinglowwould result inthisscenario.Page14 1/2008 SequoyahSRONRCExam 02/08/2008 Question NO.6 Tier 1 Group_1_KIAAPE022 AA2.03LossofRx CoolantMakeup,Abilityto determine and interpretthefollowingasthey applytothelossofReactor Coolant PumpMakeup:Failuresofflowcontrolvalveor controller ImportanceRating:3.1I3.6 Technical

Reference:

TI-28Att9.

1-47W611-68-2 AOP-I.04 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPT200.PZRLCS, B.5 Question Source: Bank#_X__ModifiedBank#

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New-----QuestionHistory:SQNNRCEXAM 1/2008,SEQBankPZR LEVEL-B.12.D 1 Question Cognitive Level:Memoryor fundamental knowledge_ComprehensionorAnalysisX10CFRPart55Content:

Comments:(CFR43.5 I 45.13)Page15 1/2008SequoyahSRONRCExam 02/08/20087.Unit1at100

%power.All conditionsarenormalwiththe following exceptions:07:00,1ARHRPumpistaggedduetomotor repairandwillbereturned to servicein24hours.08:00,Unit1hasa reactortripandSIduetoaLOCA.

08:01, E-O, ReactorTriporSafetyInjection,isenteredfollowedbya transitiontoE-1,Lossof Reactor or Secondary Coolant.08:08,The1BRHRPumptripson overcurrentduetoalockedrotor.08:14,Step15ofE-1, transitionscrewtoECA-1.1,LossofRHRSump Recirculation.

The conditionsatthe transition are:*RCSpressureis160psig

• Containmentpressureis9.7psidandstable

• RWSTlevelis 580/0 and dropping*Containmentsumplevelis 25%andrisingAssumingtheplant conditionremainunchanged,andALLECA-1.1stepsto address ContainmentSprayPump operationarecompleted,howmany containment spraypumpswillberunningandwhatwillbethesuctionsourcetothepumps?

Number of Pumps Running Suction Source A.1 RWST B.1 Containment sump C.2 RWST2 Containment sumpPage16 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,Duetothe requirements ofECA-1.1,with containment pressure greater than 9.5 psid butlessthan12.0psid,one ofthetwo containment spray pump should be shutdownbutwith stated containmentsumplevel,thesuctionwouldbe transferredtothe containmentsumpandboth pumps placedinservice.SuctionwouldnotbefromtheRWST.Plausible becausethesuctionpathwouldnotbe swappedtothe sumpsinECA-1.1and only 1 pumpwouldbe running with conditions other than statedinthestem.

B.Incorrect.Duetothe requirements ofECA-1.1,with containment pressure greater than 9.5 psid butlessthan12.0psid,one ofthetwo containment sprayshould be shutdownbutwith stated containmentsumplevel,thesuctionwouldbe transferredtothe containmentsumpandboth pumps placedinservice.Plausible becauseonlyone pumpwouldberunningwith conditions other than statedinthestemand candidate may not relate placing the stopped pump backinservicewhenthethe suctionpetri is swappedtothe sumpsinECA-1.1.

C.Incorrect.Duetothe requirements of ECA-1.1, containment pressurewouldhavetobe greaterthan12.0 psidtorequire 2 containment spray pumpstoberunning and alignedtotheRWST.Theconditions statedinthestemwould resultinone of the pumps beingstopped,thenwiththe level statedinthe conieinmentsump,the suction swappedtothe containment sump and and both pumps placed back inservice.Plausible ifcandidateis not aware relationship between containment pressure and the number of pumps that shouldbeinserviceoris not aware of thesumplevel requiredtoswapthesuctiontothesump.D.Correct, 2 containment spray pumpswouldbe running andthesuctionpathwould be swappedtothesumpinECA-1.1withthe conditions statedinthestem.Page17 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.7 Tier_1_Group_1_KIAAPE025 AK2.05LossofRHRsystem, Knowledgeofthe interrelationsbetweentheLossofResidualHeatRemovalSystemandthefollowing, ReactorBuildingSump ImportanceRating:2.6 I 2.6 Technical

Reference:

ECA-1.1,LossofRHRSump Recirculation Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPL271ECA-1.186 Question Source: Bank#----ModifiedBank

1. X_New----QuestionHistory:SQNNRCEXAM 1/2008,SQNBank ECA-1.1-B.2 002 Question Cognitive Level:.Memoryor fundamental knowledge_ComprehensionorAnalysisX10CFRPart55Content:

Comments:(CFR41.7 I 45.7)Page18 1/2008SequoyahSRONRCExam 02/08/2008 8.FollowingatotallossofallACpower,the operator is directedtoisolateCCStotheRCPthermal barriers per ECA-O.O,"Lossof ShutdownPower".Whenoffsitepowerisrestored,the operatorisdirectedinECA-0.1,"Recovery fromLossofShutdownPower withoutSIRequired",toensurethattheRCP thermal barrier isolationiscompletepriorto restartingaCCSpump.WhichONE(1)ofthefollowing describes the basis, for isolatingtheCCS thermal barrierreturnpriortorestartingtheCCSpump?A.To prevent thermalshocktotheRCPpump impelleruponrestartoftheCCSsystem during recovery.B.Toprevent thermalshocktotheRCPseal packagesuponrestartoftheCCS system during recovery.C.Toensure elevatedheatloadsasaresultofthelossofallACpowerarewithinthe design cooling capacityofCCSpriorto startingaCCSpump.Topreventsteamfromformingand circulatingintheCCSsystemand ensurestheCCSsystemis availabletocool equipment necessary for recovery.A.Incorrect,Plausibleduetotheseal package does allowforcoolingthe pump shaft, howeveritis notthereason.

B.Incorrect, PlausibleduetoIsolatingthe thermal barrierdoessecurecoolingflowtothe seal packages, howeveritis notthereason.

c.Incorrect, Plausibledueto Isolating the thermal barrierwouldreducethe heat loadontheCCS buttheisolationis nottoensuretheloadsarewithin the capacity of theCCSsystem.D.Correct,To preventsteamfromformingand circulatingintheCCSsystem and ensurestheCCSsystemisavailabletocool equipment necessary for recovery.Page19 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.8 Tier_1_Group_1_KIA 026 AK3.03Lossof ComponentCoolingWater:

Knowledgeofthe following responsesastheyapplytotheLossof ComponentCoolingWater:

Guidance actionscontainedinEOPforLossofCCW.

ImportanceRating:4.0I4.2 Technical

Reference:

ECA-O.O,LossofAllAC Power EPM-3-ECA-0.0, Basis Document for ECA-O.OLossofAllACPower Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

Question Source: 271 ECA-O.O B.4 Bank#_X_ModifiedBank#

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New-----QuestionHistory:SQNNRCEXAM 1/2008,WBNBank ECAOOOO.08 5 QuestionCognitiveLevel:Memoryor fundamental knowledge X ComprehensionorAnalysis

_10CFRPart55Content:

Comments: (CFR 41.5,41.10 145.6 145.13)Page20 1/2008 SequoyahSRONRCExam 02/08/20089.Giventhe following:

Reactor at 85%RTP stable conditions for10days.-Both Pressurizer Spray Valve Controllers in MANUAL and outputsetto"0".-All other systems and controllersinnormal alignment.

WhichONE(1)of the followingwouldbethe immediate effectifthe Pressurizer Master Pressure Controllerwasplacedin MANUALandthe outputisraisedto100 0/0?A.Pressurizer PressureHIalarm,andActual pressurizer pressurestartstorise.Pressurizer PressureHIalarm,andActual pressurizer pressurestartstodrop.

C.Pressurizer Pressure Laalarm,andActual pressurizer pressurestartstorise.

D.Pressurizer Pressure Laalarm,andActual pressurizer pressure startstodrop.A.Incorrect,TheHi pressurealarmisactuated.

Heaters do not energize but plausible if theydidthe pressure would starttoriseandhigh pressure alarmcouldcomein because the sprayvalvesarein manual and will not open.B.Correct,TheHi pressurealarmis actuated by the output of the controller as the outputisincreased,variable heatersalldeenergize,withNO heaters the pressurizer pressure will starttodropdueto ambient losses and pressurizer spray bypass flow.C.Incorrect,low pressurealarmcomesfromthe output of the controller dropping and the controller outputisbeing raisedto100%, Heaters do notenergize(butif theydidthe pressurewouldrise).

Plausible to conclude that raising controller output could result in raising pressure.D.Incorrect, low pressurealarmcomesfromthe output of the controller dropping and the controller outputisbeing raisedto100%, Heatersdodeenergize and the pressuredoesdrop.Plausibleto conclude that the heaterwoulddeenergize causing pressure to lower andthelow pressurealarmtocomein.Page21 1/2008 SequoyahSRONRCExam 02/08/2008 Question No.9 Tier_1_Group_1_K/AAPE027AA1.02 PressurizerPressureControlSystemMalfunction,Abilityto operateand/or Monitorthefollowingastheyapplytothe PressurizerPressureControl Malfunction:

SCR-controlledHeatersinmanualmode.ImportanceRating:3.1/3.0 Technical

Reference:

AOP-1.04, Pressurizer InstrumentandControl Malfunctions Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:QuestionSource:

OPT200.PZRPCSB.4,B.5Bank#X---ModifiedBank#

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New-----QuestionHistory:SQNNRCEXAM1/2008,WBNBank SYS068C.22 20QuestionCognitiveLevel:Memoryor fundamentalknowledge_

ComprehensionorAnalysis

__X__10CFRPart55Content:41.7/45.5/45.6Comments:Addedbulletinstem concerninqCBankBackup heaterbeingoutofservice.Ifontheywouldnotturnoffonincreasing output of controllerandadded'available'ineachchoice.Page22 1/2008SequoyahSRONRCExam 02/08/200810.TheCROisperforminganRCScooldowninresponsetoaSteam Generator tuberupture.Theoncomingshifthasarrivedinthecontrolroomforturnover.

In accordancewithOPDP-1,whichONE(1)ofthefollowing identifies turnover requirements?An operatorisNOTpermittedto simultaneously turnoverandperformthe cooldown;AControlBoard WalkdownandaLogReviewbytheoncoming operator arerequiredtobecompleted.B.An operatorisNOTpermittedto simultaneously turnoverandperformthe cooldown;AControlBoard Walkdownbytheoncoming operatorisNOTrequiredprovidedtheLogReviewiscompleted.C.An operatorispermittedto simultaneously turnoverandperformthecooldown;AControlBoard WalkdownandaLogReviewbytheoncoming operator arerequiredtobecompleted.D.An operatorispermittedto simultaneously turnoverandperformthecooldown;AControlBoard Walkdownbytheoncoming operatorisNOTrequiredprovidedtheLogReviewiscompleted.Page23 1/2008SequoyahSRONRCExam 02/08/2008A.Correct,PerOPDP-1, Operations personnel performing shift turnover will not be involved in plant evolutions/activities during performanceonshift turnoveractivities.TheCooldown should be complete prior to conducting turnover.TheOPDPalso requires a log review and a control board walkdownasa part of turnover.B.Incorrect,The cooldown should be completed priortoturnover,thereisno provision for not completing the boardwalkdown.Plausibleduetocandidatecouldthinkthatdueto beinginan emergency the walkdown would not be required.c.Incorrect,Plausibleduetocandidate not knowing requirement that personnel will not be involvedinactivitiesduringturnover, and candidatecouldthinkthatsincethecooldown should not be delayed that turnovercouldbe conductedinparallel.

D.Incorrect,Plausibleduetocandidate not knowing requirement that personnel will not be involvedinactivitiesduringturnover, and candidatecouldthinkthatsincethe cooldown should not be delayed that turnovercouldbe conducted in parallel andthatdueto beinginan emergency thewalkdown'would not be requiredPage24 1/2008 SequoyahS'RONRCExam 02/08/2008 QuestionNo.10 Tier_1_Group_1_K/A038G2.1.3 Steam GeneratorTubeRupture, ConductofOperations, Knowledgeofshift turnover practices.

Importance Rating: 3.0/3.4 Technical

Reference:

OPDP-1, ConductofOperations,Rev8 Proposed referencestobeprovidedto applicants during examination:

None LearningObjective:OPL271C209B.10 x Question Source: Bank#-----ModifiedBank#

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New----Question History:NewforSQNNRCEXAM1/2008 QuestionCognitiveLevel:Memoryor fundamental knowledge X ComprehensionorAnalysis

_10CFRPart55Content:(CFR:41.10/

45.13)Comments:Page25 1/2008SequoyahSRONRCExam 02/08/200811.Giventhe following-A Reactor Trip/SafetyInjectionwas initiatedonUnit2duetoasteamlinebreakonSteam Generator#1 outside containmentbutupstreamoftheMSIV.-Thecrewrespondedin accordancewiththe emergerency operating procedures.

When Steam Generator#1blowdownwas completetheRCS conditionswereasfollows:

Pressurizerpressure1880psig.

Pressurizerlevelg%.Lowest ReS Tcold temperaturereachedwas474°F.WhichONE(1)ofthefollowing identifiestheconcernwhenthesteam generator blowdownwascomplete following isolationandthe condition(s)requiredto re-energize the pressurizer heaters?Concern when blowdown completeA.Steam Generator tube failure duetohigh differential pressure.B.Steam Generator tube failure duetohigh differential pressure.Pressurizer overfillandRCS.pressurization.

D.Pressurizer overfillandRCS pressurization.

To re-energize heatersRestorelevelto

>17%andResetSIRestorelevelto

>17%SIresetNOTrequiredRestorelevelto

>17%andResetSIRestorelevelto

>17%SIresetNOTrequiredPage26 1/2008 SequoyahSRONRCExam 02/08/2008 A.Incorrect;Plausibleif student does not understand the Pressure dynamics of theRCSvs SG pressuresduringgivenevent.Alsoif student does not knowSIwould lockoutthe pressurizer heaters and must be reset before heaterwouldenergize.

B.Incorrect;Plausibleif studentdoesnot understand the Pressure dynamics of theRCSvs SG pressuresduringgivenevent.

C.Correct;Per EPM-3-E-2forSIterminationis checkedtominimizethe likelihood of overfillingthepressurizer.

Pressurizer level must be>17%and SI reset for Pressurizer heaterstoenergize.

D.Incorrect; First part correct Per EPM-3-E-2forSI termination is checkedtominimize the likelihood of overfillingthepressurizer.

Second part incorrect, plausible if student does not knowSIwouldlockoutthe pressurizer heaters and must be reset before heaterwouldenergize.Page27 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.11 Tier_1_Group_1_KIA 040 AK1.03 SteamLineRupture, Knowledgeofthe operational implicationsofthe following conceptsasthey apply to Steam Line Rupture: RCS Shrink and consequent depressurization.

ImportanceRating:3.8I4.2 Technical

Reference:

EPM-3-E-2step7, 1-47W611-68-2 Proposed referencestobe provided to applicants during examination:

None Learning Objective:OPL271E-2b.6, OPT200PZRPCS b.4 Question Source: Bank#_ModifiedBank#-----NewX---QuestionHistory:SQNNRCEXAM 1/2008, Question Cognitive Level: Memory or fundamental knowledge X Comprehension or Analysis_10CFRPart55 Content: Comments: 41.8 141.10 145.3Page28 1/2008SequoyahSRONRCExam 02/08/200812.Giventhe followingUnit1plant conditions:

ECA-O.O,LossofAllACPowerisineffect.

DepressurizationofallintactSGsisinprogress.-TheSGaretobe depressurizedatthe"maximumrate".WhichONEofthe following identifies the parameterusedto determinethemaximumrateandthebasisforthe parameterbeingthelimiting parameter?

A.Ability to maintain pressurizerlevelabove 100/0 to preventlossofpressurecontrolresultingin reactorvesselheadvoiding.AbilitytomaintainatleastoneSG narrowrangelevelabove 100/0topreventlossof sufficient heat transfer capabilityfromtheRCS.

C.Ability to maintainRCSTcoldcooldownequaltoorlessthan 100°F/hourtoprevent transitiontoFR-P.1, PressurizedThermalShock.

D.Ability to maintain RCS pressureequaltoor greaterthan200psigtopreventnitrogenfrom enteringthetheRCSfromCLAs.Page29 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect.Theabilitytomaintain1SGlevelabove10%

narrowrangeisthe parameter.

Loss of pressurizer level and reactor vessel head voiding may occur and are acceptableduringthe depressurization may stated in a note preceedingstepto depressurize the SGs.Maintaining pressurizer level10%or greater is a parameter monotoredintheEOPsthat resultsinactions being taken.B.Correct.The abilitytomaintain1SG levelabove10%narrowrangeisthe parameter andthebasisisto preventtheloss of sufficient heat transfer capabilityfromtheRCS.

c.Incorrect.The abilitytomaintain 1 SGlevelabove10%

narrowrangeisthe parameter, NOTtheTcold cooldownrate.PTSis avoided by stopping the cooldown before reaching PTS temperaturesandtheFRGsare suspended during ECA-O.O implementation.

D.Incorrect.The abilitytomaintain1SG levelabove10%narrowrangeisthe parameter.

The depressurizationwouldbe stopped andtheRCS pressure controlled between 100 and200psig.If the pressureweretodropto below100psig prior to isolating CLAs, nitrogen could be injectedintotheRCS as described in a Caution priortothestepfor depressurizingthe SGs.Page30 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.12 Tier_1_Group_1_KIA 055 G2.4.18StationBlackout, KnowledgeoftheBasisforEOPs.ImportanceRating:2.7I3.6 Technical

Reference:

ECA-O.O,LossofAllACPower EPM-3-ECA-0.0 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPL271 ECA-O.O,Obj1.b,3.b,8QuestionSource:

Bank#_ModifiedBank#X

__New_QuestionHistory:SQNNRCEXAM 1/2008,Sequoyahbankquestion ECA-0.0-B.1.B 002 modified Question Cognitive Level:Memoryor fundamental knowledge X ComprehensionorAnalysis

_10CFRPart55Content:(CFR:41.10 145.13)Comments: Sequoyahbankquestion ECA-0.0-B.1.B 002modifiedPage31 1/2008 SequoyahSRONRCExam 02/08/200813.Giventhe following conditions:ALossofOffsitePoweroccurred RCS pressureis2085psigThotis573°FCoreexit thermocouplesare583°F WhichONE(1)ofthefollowingistheclosest approximation of ReS subcooling?

A.Incorrect.

Plausible if 15 is subtracted from initial pressure when calculating saturation temp andusingincore temperature 641°F-583°F=58°F B.Correct.(2100psiaTsat

=643°F)643°F-583°F=60°F C.Incorrect.

Plausible if 15 is subtracted from initial pressure when calculating saturation temp andusingThot instead of incore temperature 641°F-573°F=68°FD.Incorrect.

Plausible ifThotis used instead of incore temperature 643°F-573°F=70°FPage32 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.13 Tier_1_Group_1_KIA 056 AK1.03Lossof off-site Power, Knowledgeofthe operational implicationsofthefollowing conceptsastheyapplytoLoss of Off-SitePower:Definitionof Subcooling:useofsteamtablesto determine itImportanceRating:3.1I3.4 Technical

Reference:

ES-0.2NaturalCirculationCooldown.SteamTables Proposed referencestobeprovidedto applicants during examination:SteamTablesLearningObjective:

OPL271 ES-O.2QuestionSource:Bank#X---ModifiedBank

1. -----New----QuestionHistory:SQNNRCEXAM 1/2008,056 AK1.03PrairieIslandUnit12004NRC EXAM Question Cognitive Level:Memoryor fundamental knowledge_ComprehensionorAnalysisX10CFRPart55 Content: Comments:(CFR41.8 I41.10/45.3)

Page 33 1/2008SequoyahSRONRCExam 02/08/200814.Giventhe following plant conditions:Units1and2are operating at 1000/0powerwithNoTechSpecLCOactionsineffect.-The125VDCPowerSystemisnormallyalignedwiththeexceptionofthe Vital BatteryBoardIV,whichisbeingsuppliedfromtheVitalBatteryVandand2-SVital Battery Charger.-Offsite powerislost.1A-Aand2B-Bdiesel generatorsstartandload.1B-Band2A-Adiesel generatorsfailtostart.Ifoffsitepowerhasbeenlostfor longerthan4hours,whichONE(1)ofthe following statements identifies the conditionofthe 125VVitalDC batteries?(AssumeNO operatoractionistaken).A.Allfour125vVitalDC Batterieswouldbeat their normal voltage requirements.B.Allfour125vVitalDC Batterieswouldbe dischargedbeyonddesignlimits.

CY'125vVitalDC BatteriesIandIVwouldbeat their normal voltage requirements.125vVitalDC BatteriesIIandIIIwouldbe dischargedbeyonddesignlimits.D.125vVitalDC BatteriesIIandIIIwouldbeat their normal voltage requirements.125vVitalDC BatteriesIandIVwouldbe dischargedbeyonddesignlimits.Page34 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,whilethe125vVital boards I andIVwouldhave power availabletotheir charger,theIIandIII boards would nothavepower.With power availabletothechargers,theI and IV batterieswouldbecharged, buttheII and III batterieswouldbedischarged.Plausible if the cendkiete confuses the power supplytothe chargersorrealizesthe chargershavean alternate power supplies(whichare availablefortheIIandIII boards)but does not recall that manualactionwouldbe requiredtoplacethe alternate power supplyinservice.

B.Incorrect,whilethe125vVital boards I andIVwouldhave power availabletotheircharger,theIIandIII boards would nothavepower.With power availabletothechargers,the I and IV batterieswouldbecharged, buttheII and III batterieswouldbedischarged.Plausible ifthecandidate concludesthatthe 480v boards that supply the battery chargers do not sequence backonwhenthe DG recovers the board.C.Correct,as identified on 1,2-45N700-1,the125vVital boardsIandIVwouldhave powertothe battery chargerwhilethe battery chargersforII andIIIwouldbedeenergized,thustheIandIV batterieswouldbe charging and keeping the board powered,whiletheVital Batteries Boards II and III, without a batterycharger,wouldbelostasthe batteries discharged.

D.Incorrect,the125vVital boards II andIIIwould NOT have powertothe battery chargerwhilethe battery chargersforI andIVwouldbeenergized,thustheI and IV batteries would be chargingandkeepingthe board powered,whiletheVital Batteries BoardsIIandIII, without a batterycharger,wouldbe lostasthe batteriesdischarged.Plausible if the candidate reverses the chargersthathave power availabletothem.Page35 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.14Tier1Group1 KIA058AK1.01LossofDCPower:knowledgeofthe operational implicationsofthefollowingconceptsasthey applytoLossofDCPower:Battery charger equipment and instrumentation.ImportanceRating:2.8I3.1 Technical

Reference:

1,2-45N700-1FSAR8.1.4 1-AR-M1-C AOP-P.02 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:OPT200.DC,b.4,b5 Question Source: Bank#XModifiedBank

1. -----New-----QuestionHistory:SQN N.RC EXAM 1/2008,SQN Bank DC-B.O 002QuestionCognitiveLevel:Memoryor fundamental knowledge_Comprehension or Analysis X10CFRPart55Content:(CFR41.8 I 41.10 145.3)Comments:reworded question to address the conditionofboththebatteriesandthebattery chargers after greaterthan4hoursofDCloadbe suppliedbythebatteriesboard.Page36 1/2008 SequoyahSRONRCExam 02/08/2008 15.WhichONE(1)of the following conditions would require entryintoTech Spec 3.7.5, Ultimate Heat Sink?A.Water level of675ftand ERCW supply temperature of 81.5°F.B.Water level of677ftand ERCW supply temperature of 82.5°F.Waterlevelof679ftand ERCW supply temperature of 83.5°F.D.Waterlevelof681ftand ERCW supply temperature of 84.5°F.Questionrequiresthecandidateto recallboththe temperature and level requirements oftheUHS.with water temperature above 83degrees,the river level must be greater than 680'andthe temperature equaltoorlessthan 84.5 degrees.If temperatureisless than 83 degrees the requirement for riverelevationis 670'orgreater.A.Incorrect.Both level and temperaturearewithinthelimitsrequired.Plausible because candidate could notbecertainwherethe temperature requirement changeddueto river level or may notknowthe minimum level requirement.

B.Incorrect.Both level and temperaturearewithinthelimitsrequired.Plausible because candidate could notbecertainwherethe temperature requirement changeddueto river level.C.Correct.A temperature of 83.5 degreesisabovethelimitwiththe riverlevellessthan680'.D.Incorrect.Both level and temperaturearewithinthelimitsrequired.Plausible because the temperature listedisthe highest temperature and candidate may not recall the higher temperature is allowedwiththe riverlevelabove 680'or may not recallthatthereare provisions for exceeding the lowerlimitlistedinthetechspec.Page37 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.15 Tier_1_Group_1_KIA 062AA1.01Lossof NuclearServiceWater,Abilityto operate and I or monitor the following as they applytotheLossof Nuclear Service Water: Nuclear Service water temperature indication ImportanceRating:3.1I3.1 Technical

Reference:

Tech Spec 3.7.5 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.ERCW B.6 Question Source: Bank#-----ModifiedBank

1. X----New-----QuestionHistory:SQNNRCEXAM 1/2008,SQNBankModified ERCW-B.6 001 Question Cognitive Level: Memory or fundamental knowledge X Comprehension or Analysis_10CFRPart55 Content: Comments:(CFR41.7 I 45.5I45.6)Page38 1/2008SequoyahSRONRCExam 02/08/200816.Giventhe following plant conditions:-ALossOf Coolant Accident (LOCA)outside containmenthasresultedinRCS Subcooling droppingto0 degrees F.-The operatingcrewisperformingthe actionsofECA-1.2,LOCA Outside Containment.-Actionsarebeingtakentoisolatetheleak.

In accordancewithECA-1.2"LOCA Outside Containment,"whichONE(1)ofthe followingistheinitial mitigating strategyandwhatwouldbethe indicationusedtoconfirmtheLOCAhasbeen isolated?A.EnsureRHRsuctionfromRCSIsolated PressurizerlevelrisingEnsureRHRsuctionfromRCSIsolatedRCSpressurerisingC.IsolateRHRColdLegInjection PressurizerlevelrisingD.IsolateRHRColdLegInjectionRCSpressurerisingPage39 1/2008 SequoyahSRONRCExam 02/08/2008 A.Incorrect; Plausible if student remembersthattheinitial strategy of ECA-1.2istoEnsureRHRsuctionisolationfromtheRCS but does not rememberthattheindicationisRCS pressure increasing.

Pressurizerlevelrisingis plausiblesincethe student could reasonthatit mayberising iftheleakwasisolated.The proceduredirectstheuse of RCS pressure increasing as the methodusedtoindicatetheleakhasbeenisolated.

B.Correct;The proceduredirectstheinitial strategy of ensuringRHRsuction isoietionfromtheRCS andtheuse of RCS pressure increasing as the methodtoindicatethe leakhasbeenisolated.

C.Incorrect; Plausible because isolation ofRHRColdLeginjectionis a strategy containedinthe procedure butitis nottheinitial mitigating strategy.Pressurizer levelrisingis a plausibleindicationsincethe studentcouldreasonthatit mayberisingiftheleakwasisolated.The proceduredirectstheuse of RCS pressure increasing as the method usedtoindicatetheleakhasbeenisolated.

D.Incorrect; Plausible because isolation ofRHRColdLeginjectionis a strategy containedinthe procedure butitis nottheinitial mitigatingstrategy.The proceduredirectstheuse of ReS pressure increasing as the method used toindicatetheleakhasbeenisolated.Page40 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.16Tier1Group1 KIA W/E04 G2.4.48LOCAOutside Containment:Abilityto interpretcontrolroom indicationstoverifythestatusandoperationofsystem,and understand how operatoractionsand directives affectplantandsystemconditions.ImportanceRating:3.5 I 3.8 Technical

Reference:

ECA-1.2 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:OPL271ECA-1.2,B.5QuestionSource:Bank#XModifiedBank

1. ----New-----QuestionHistory:SQNNRCEXAM 1/2008,Modifiedbank questionseecomments Question Cognitive Level:Memoryor fundamental knowledge__X__Comprehension or Analysis_10CFRPart55 Content: 43.5I45'.12 Comments: Questionmodifiedfrom combinationofSQNbank question ECA-1.2-B.1.A001and questioninINPObankfromDiabloCanyonUnit1 1/1999Page41 1/2008 SequoyahSRONRCExam 02/08/2008 17.WhichONE(1)ofthe followingisan adverse consequencethatcouldresultfrom delayingfeedandbleedcoolingifthe conditions to initiatefeedandbleedaremetinFR-H.1,"Lossof Secondary Heat Sink"?A.High Temperature induced failure of S/GU-tubebends.B.An overpressurization challengetothe Reactor Vessel.Inability to prevent or minimize core uncoveryduetohighRCS pressure.D.Inability to recover the S/Gs without damagefromhigh thermal stressescausedby cold water refill.A.Incorrect,PlausibleduetoV-tube uncovery with assumedRCShighTempduetoloss of cooling.B.Incorrect,Plausibleduetoloss ofcoolingtoRCS and assumed RCS pressureriseduetoloss of cooling.C.Correct,Per EPM-3-FR-H.

1.In ordertominimizecore uncoveryduetoloss of heatsink,the operator must identify loss of heat sink conditions and immediatelyinitiatefeed and bleed.D.Incorrect,Plausibledueto possible S/G dryout with subsequent refill.Page42 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.17 Tier_1_Group_1_KIA W/E05 EK3.1Lossof SecondaryHeatSink, Knowledgeofthereasonsforthe following responsesasthey applytotheLossof SecondaryHeatSink:Facility operating' characteristics during transient conditions, including coolant chemistryandthe effects of temperature,pressure,and reactivity changes and operating limitationsandthereasonsforthese operating characteristics.

ImportanceRating:3.4I3.8 Technical

Reference:

EPM-3-FR-H.1, page 12, step 5 note 1 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPL271 FR-H.1 8.6 Question Source: Bank#X---ModifiedBank#

---

New-----QuestionHistory:SQNNRCEXAM 1/2008, SQN BankFR-H.1-03 001 Question Cognitive Level:Memoryor fundamental knowledge X Comprehension or Analysis_10CFRPart55 Content: Comments:(CFR41.5 I41.10,45.6, 45.13)Page43 1/2008SequoyahSRONRGExam 02/08/200818.Giventhe following conditions:At0900the Reactor Tripsdueto2droppedrods.At0920asmallbreakLOGAoccurs.At0950thecrew transitionedtoEGA-1.1,"LossofRHRSump Recirculation",duetothe failureofbothRHRpumps.GrewhasreducedEGGSflowto1SIPand1GGPperEGA-1.1.SIflowcannotbe terminatedduetolackof subcooling.At1030thecrewis performing EGA-1.1Step20RNOto establish the minimumrequiredEGGSflowtoremove decay heat.Whichoneofthe following correctly describestheflowratethatmeetstheintentofEGA-1.1,Step20RNO,AND requirementsofusingEGGSpumpsinmeetingthisflow rate?REFERENCE PROVIDED A':IEstablish325gpmEGGSflow.EGGSpumpsmaybestartedandstoppedas necessary to accomplishthedesiredflowrate.B.Establish325gpmEGGSflow.EGGSpumpsareNOTpermittedtobestartedandstoppedas necessary to accomplishthedesiredflowrate.G.Establish400gpmEGGSflow.EGGSpumpsmaybestartedandstoppedas necessary to accomplishthedesiredflowrate.D.Establish400gpmEGGSflow.EGGSpumpsareNOTpermittedtobestartedandstoppedas necessary to accomplishthedesiredflowrate.Page44 1/2008 SequoyahSRONRCExam 02/08/2008A.Gorrect.0900

-1030(90Min)UsingEGA-1.1,curve 9,thevalueis approximately325gpm.TheBasisstates"the operatoristhen instructed to establishtheminimumEGGSflow neededtomatch decay heat in order to further decreaseEGGSpump Flow and delay RWSTdepletion.This value, of 325gpmisinthe acceptable regionusingthegraphfromtime of trip AND meets the requirement of Minimum Flow to delay RWSTdepletion.The procedurestatesEGGS pumps may be started and stopped as necessary to accomplish the'desiredflowrate.B.Incorrect.

Gorrectflowratewrongaction.Plausible if student does not know procedure requirementtostartorstop pumps as neccessarydueto aLOGA.The student maythinkthatdueto a LOGA pumps must notbestopped.

G.Incorrect.Plausibledueto400gpm meetsthecurve requirment howeveritdoes not meet the intent ofthestepwhichisto meet the minimum flow requirementswhilestill meetingthecurverequirments.

Second part correctinEGGS pumps may be started and stopped as necessary to accomplish the desiredflowrate.D.Incorrect.Plausibledueto400gpm meetsthecurve requirment howeveritdoes not meet the intent ofthestepwhichisto meet the minimum flow requirementswhilestill meetingthecurverequirments.Plausibleif student does not know procedure requirementtostartorstop pumps as neccessarydueto aLOGA.The student may thinkthatdueto a LOGA pumps must notbestopped.Page45 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.18 Tier_1_Group_1_KIA W/E11 EK2.2Lossof Emergency Coolant Recirculation, Knowledgeofthe interrelations betweentheLossof Emergency Coolant Recirculationandthe following:

Facility's heat removal systems, including primary coolant, emergencycoolant,the decay heat removal systems, and relations between the proper operationofthese systemstothe operation ofthefacility.

ImportanceRating:3.9 I 4.3 Technical

Reference:

ECA-1.1,Curve9 Proposed referencestobe provided to applicants during examination:

Provide ECA-1.1, CurveLearning Objective:OPL271ECA-1.1,B.6 Question Source:Bank#_Modified Bank#__X__New-----QuestionHistory:SQNNRCEXAM 1/2008,WBNNRCEXAM2006 WE11G2.1.13.

Modified Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis__X_10CFRPart55 Content: Comments:(CFR41.7 I 45.7)Page 46 1/2008SequoyahSRONRCExam 02/08/200819.Giventhefollowing:Unit1 operating at 50%powerRodcontrolinAUTOwithBank 0at176steps-Tavg auctioneeringunitfailsLOW WhichONE(1)ofthefollowing identifieshowtherodcontrolsystemwill respond ANDwhatthe indicationwillbeon1-M-4?A.RodsinsertingasindicatedbyRODSIN'RED'lightLITB.RodsinsertingasindicatedbyRODSIN'GREEN'lightLITRods withdrawingasindicatedbyRODSOUT'RED'lightLITD.Rods withdrawingasindicatedbyRODSOUT'GREEN'lightLITPage47 1/2008SequoyahSRONRCExam 02/08/2008A.Incorrect, IftheTavg AuctioneeringUnitfailedlow,therod control systemwouldseelarge error betweenTref-Tavgcausingtherods start withdrawing notinserting.However,if conditions existedthatdid result intherods insertingthe'RODSIN'green lightindicationwouldbeilluminated, butthelightisgreen notred.Plausible ifthecandidate confuses the direction of rod movementandthe color ofthe'RODSIN'lightwiththe color ofthe'RODS OUT'lightwhichisred.

B.Incorrect, IftheTavg AuctioneeringUnitfailedlow,therod control systemwouldseelarge error betweenTref-Tavg causingtherodsstart withdrawing notinserting.However,if conditions existedthatdid result intherods insertingthe'RODSIN

'greenlightindicationwouldbeilluminated.Plausible becausethecandidate couldconfusethedirection of rod movement but correctly identify the color ofthe'RODSIN'lightbeinggreen.

C.Correct, IftheTavg AuctioneeringUnitfailedlow,therod control systemwouldsee a large error between Tref-Tavgcausingtherodsto start withdrawing.

Rod withdrawalcausesthe'RODS OUT'redlighttobe illuminated.D.Incorrect, IftheTavg AuctioneeringUnitfailedlow,the rod control systemwouldseelarge error betweenTref-Tavg causingtherods startwithdrawing.The'RODS OUT'wouldbe illuminated butthelightisred not green.Plausible ifthecandidate determines the correct direction of rod movement but confuses the color ofthe'RODS OUT'lightwiththe color ofthe'RODSIN' lightwhichisgreen.Page48 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.19Tier1Group2K/A001AK2.05 Knowledgeofthe interrelationsbetweenthe Continuous Rod Withdrawalandthe following:RodmotionlightsImportanceRating:

2.9/3.1 Technical

Reference:

FSARSection7.7.1TI-28,CurveBook, Attachment 9, Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:QuestionSource:

OPT200RDCNT B.5.d Bank#-----ModifiedBank#X

--NewQuestionHistory:SQNbank questionRDCNTB.14.d011mod forSQNNRCEXAM1/2008QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysis

_X__10CFRPart55Content:

Comments: 41.7/45.7Page49 1/2008 SequoyahSRONRCExam 02/08/200820.Giventhe following plant conditionsforUnit2: IntermediateRangeN36failedhigh.

OperatorsplacedtheleveltripbypassswitchforN36tothebypassposition.

Subsequently the ReactortripsduetoLargeBreakLOCA.

WhichONE(1)ofthefollowing describes the operationofsourcerange instrumentstobeusedto monitor the SubcriticalityStatusTree?A.SourceRangechannelN31andN32are automaticallyreinstatedwhenpower decreases below P-10.B.SourceRangechannelN31andN32are automaticallyreinstatedwhenpower decreases below P-6.Both SourceRangechannels,N31andN32,mustbe manually reinstatedwhenthe operable IntermediateRangechannel(N35) decreasesbelowtheP-6setpoint.D.Both SourceRangechannels,N31andN32,mustbe manually reinstatedwhenthe operable IntermediateRangechannel(N35) decreasesbelowtheP-10setpoint.A.Incorrect,Sourcerange channels are not reinstateduntiltheIRMsdrop below theP-6setpoint.WithoneIRMfailedhightheSRMs cannot automatically reinstate.

Plausible becausetherein aP-10backupto ground the output oftheSRMs as power increasescausingthe SRMs output to readzero.This backup signal is automatically removed as the P-10 clears B.Incorrect,Sourcerange channels are normally reinstated automaticallywhenboth oftheIRMsdrop belowtheP-6setpoint.WithoneIRMfailedhighthe SRMscannot automaticallyreinstate.Plausible becausetheSRMtripcanbe blocked as power increaseswhenoneIRM increasesabovetheP-6 setpoint and the candidate couldconfusethe 1 out of 2 requirementgoingupwiththe 2 out of 2 requirement coming down.C.Correct,withone oftheIRMsfailedhigh, manual reinstatement oftheSRMis required.D.Incorrect,SRMare automatically reinstatedwhentheIRMdrop belowtheP-6 setpoint, not belowtheP-10setpoint.Plausible becausethecandidate couldmistakethe 2 setpoints.Page50 1/2008*SequoyahSRONRCExam 02/08/2008QuestionNo.20 Tier_1_Group--L KIA033G2.4.21Lossof IntermediateRangeNI:Knowledgeofthe parametersandlogicusedtoassessthestatusofsafetyfunctionsincluding:1.

Reactivitycontrol,2.Corecoolingandheatremoval,3.ReactorCoolantsystemintegrity,4.

Containment Conditions,S.

Radioactivityreleasecontrol.ImportanceRating:3.7I4.3 Technical

Reference:

AOP-1.0,NuclearInstument Malfunction,Rev8page9 1 ,2-47W611-99-2Rev13 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:OPL271AOP-1.01,B.8QuestionSource:

Bank#-----ModifiedBank#

X----New-----QuestionHistory:SQNNRCExam 1/2008,SQNBankModifiedNIS-B.2.007QuestionCognitiveLevel:Memoryor fundamental knowledge__X__ComprehensionorAnalysis

_10CFRPart55 Content: Comments:(CFR43.5 I 45.12)Page51 1/2008 SequoyahSRONRCExam 02/08/2008 21.Given the following:-Unit1isinMode6and currently loadingfuelintothecore.-IceisbeingblownintotheIce Condenser Baskets.-A previous cycle fuel assembly is dropped during transfertoitscore location.-Bubblescanbeseen risingfromthe dropped fuel assemblyandArea Radiation Monitorsgointohighalarm.

In accordance with AOP-M.04, Refueling Malfunctions, all of the followingwouldbe required EXCEPT?Initiate Control Room Isolation.

B.Evacuateel.734RefuelFloor.

C.Initiate Auxiliary Building Isolation.

D.Close 1-78-610, Transfer Tube Wafer Valve.Could not identify enough plausible distractors to allow elimination of the negative approachinthe'stem ofthequestion.A.Correct,Not required by procedure.

B.Incorrect, Evacuate Aux Building el.734 RefuelFloor.Tobe performed per AOP-M.04 butPlausibledueto dropped fuel occurringinthe ContainmentBuildingandthe refuelfloorisoutsidecontainment.

C.Incorrect,Tobe performed per AOP-M.04 butPlausibledueto dropped fuel occuringinthe Containment Building.D.Incorrect,Plausible if studentthinksvalveclosurewould not be requiredsincewater level is not dropping.Page52 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.21 Tier_1_GroupK/A exposure036AK1.01FuelHandlingIncidents:

Knowledgeofthe operational implicationsofthefollowingconceptsastheyapplytoFuelHandlingIncidents:Radiation hazards.ImportanceRating:

3.5/4.1 Technical

Reference:

AOP-M.04,Refueling Malfunctions,Rev7 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPL271AOP-M.04 B.5,8QuestionSource:

Bank#_-__ModifiedBank#

_NewX--QuestionHistory:NewforSQNNRCEXAM1/2008, Question Cognitive Level:Memoryor fundamental knowledge_X_Comprehension or Analysis_10CFRPart55 Content: Comments:(CFR41.8/41.10/45.3)Page53 1/2008 SequoyahSRONRCExam 02/08/2008 22.WasteGasDecay Tank J contains high activity gas.WasteGasDecayTank J relief valve develops a largeflangeleak.

WhichONE(1)ofthe following would identify the responseoftheRad Monitors listed?A.WasteGasRad Monitor (RE-90-118)wouldalarm,butthe Auxiliary Building Ventilation Monitor(RE-90-101)would NOT alarm.B.WasteGasRad Monitor (RE-90-118)wouldalarm,andthe Auxiliary Building Ventilation Monitor(RE-90-101)wouldalarm.WasteGasRad Monitor (RE-90-118)would NOTalarm,butthe Auxiliary Building Ventilation Monitor(RE-90-101)wouldalarm.

D.WasteGasRad Monitor (RE-90-118)would NOTalarm,andthe Auxiliary Building Ventilation Monitor (RE-90-101)NOT alarm.A.Incorrect,leakage must entertheWGDTreleaselineto pass bywastegasradiation monitor RE-90-118.Flangeleakagewould not enter this line but rather the general Aux Building Spaceswhereitwould eventually pass by Aux buildingstackradiation monitorRE-90-101.Thereforeforflangeleakage,90-118 would notalarmand90-101wouldalarm.Plausibleif studentdoesnot understand the relationship betweentheventilationsystem and rad monitors.B.Incorrect,leakage must enter the WGDTreleaselineto passbywastegasradiation monitorRE-90-118.Flangeleakagewould not enterthisline but rather the general Aux Building Spaceswhereitwould eventually pass by Aux buildingstackradiation monitorRE-90-101.Thereforeforflangeleakage,90-118 would notalarmand90-101wouldalarm.Plausibleif studentdoesnot understand the relationship betweentheventilationsystemandradmonitors.

C.Correct,leakage must enter the WGDTreleaselineto passbywastegasradiation monitor RE-90-118.Flangeleakagewould not enterthisline but rather the general Aux Building Spaceswhereitwould eventually pass by Aux buildingstackradiation monitor RE-90-101.Thereforeforflangeleakage,90-118 would notalarmand90-101wouldalarm.D.Incorrect,leakage must enter the WGDT releaselineto pass bywastegasradiation monitor RE-90-118.Flangeleakage would not enterthisline but rather the general Aux Building Spaceswhereitwould eventually pass by Aux building stack radiation monitorRE-90-101.Thereforeforflangeleakage,90-118 would not alarm and90-101wouldalarm.Plausible if student does not understand the relationship betweentheventilationsystem andradmonitors.Page54 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.22 Tier_1_Group L K/A 060AA1.02 Accidental Gaseous Radwaste Release: Ability to operateand/or monitor the followingasthey apply to accidental gaseous radwaste: Ventilation system ImportanceRating:2.9/3.1 Technical

Reference:

1,2-47W830-4 1,2-47W866-1 Proposed referencestobe provided to applicantsduringexamination:

None Learning Objective:

Question Source: OPT200.GRW, B.5OPT200.RM,B.4Bank#----Modified Bank#_X__New----Question History:SQNNRCEXAM1/2008, modified from WGDS-B.3.A 006 Question Cognitive Level: Memory or fundamental knowledge X Comprehension or Analysis_10CFRPart55 Content:(CFR41.7/45.5/45.6)

Comments: modifiedfromSQN question WGDS-B.3.A 006Page55 1/2008SequoyahSRONRCExam 02/08/200823.Giventhe followingforUnit1:-Plantisat100

%power.-Containmententryisinprogressfor maintenance.-The following annunciatorsarelockedin.

-LWRPERSACCESSOUTERDRLOCK

-LWRPERSACCESS'INNERDRLOCK

-UPRILWRAIRLOCKBREACH

-Containment pressurehasrapidly equalizedwiththeAuxBuilding.

...Containment pressure currently indicates0.18PSID.In additiontoTS3.0.3,whichONE(1)ofthe.

following identifiesboth,arequiredTS entry AND its associatedactionstatement?A.EnterTS 3.6.1.4"INTERNALPRESSURE"andrestore Containment to annulus DPwithin1hour.EnterTS3.6.1.1"CONTAINMENT INTEGRITY"andrestore Containment integritywithin1hour.C.EnterTS3.6.1"CONTAINMENTAIRLOCKS"andrestoreboth ContainmentAccessdoorsto operablestatuswithin1hour.D.EnterTS3.6.1.2"SECONDARY CONTAINMENTBYPASSLEAKAGE"andrestore Secondary ContainmentBypassLeakagewithin1hour.A.Incorrect,Plausibleif student does not knowLCOfor Containment pressurewithquestionindicating rapiddropinpressure.

Containment pressure stillwithinlimits ofTechSpec 3.6.1.4 of-0.1 and0.3psig.B.Correct,DuetoNot meeting requirements of TS 3.6.1.3 per surveillance requirements of TS4.6.1.1 C.Incorrect,Plausible if student does not knowLCOfor Containment AirLocks.Thereisno 1 houractionforTS 3.6.1.3 associated with any doorsbeinginoperable.D.Incorrect,Plausible if student does not know that Containment Access doorsarenot considered bypass leakage pathstothe Auxiliary Building.Page56 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.23 Tier_1_Group--LKIA069 G2.4.45LossofCTMTIntegrity:

Abilitytoprioritizeand interpret the significanceofeach annunciatororalarm.ImportanceRating:3.3I3.6 Technical

Reference:

0-AR-M12-Cpage2,3,4,and7.Tech Specs 3.6.1.3.Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.CntmtStructure B.5&6 x Question Source: Bank#-----ModifiedBank

1. -----New-----Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis X10CFRPart55 Content: Comments:(CFR43.5 I 45.3 I 45.12)Page57 1/2008 SequoyahSRONRCExam 02/08/2008 24.During the performance of FR-C.1,"Inadequate Core Cooling" the operators are directed to starttheRCPsif Incore TCs remain>1200°F.WhichONE(1)of the following describes the purpose of startingtheRCPs?A.Provides temporary coolingtothecoreby forcing single-phase flow throughthecore.Provides temporary coolingtothecoreby forcing two-phase flow throughthecore.C.Ensure steam bubblesintheSG U-tubes are removed to maximize heat transfer for coolingthecore.D.Ensure steam bubblesintheRCS intermediatelegsare collapsed to minimize RCS flow restrictions for coolingthecore.A.Incorrect,WithTCs>1200FRCSwill not be single-phaseflowwhen pumpsarestarted.

B.Correct, Provides temporarycoolingto.thecore by forcing two-phase flowthroughthecore.

C.Incorrect, Plausibleduetoflowwill passthroughthe SG U-tubes however two phaseflowwillbe pushedthrough.Steam bubbleswillbe entrained intheRCS.StartingtheRCPswillnotensuresteam, bubblesareremoved.

D.Incorrect, Plausibledueto startingRCP'swill actually clearthewater inventoryinthe intermediate leg and permit circulation of hot gasesfromthecoretotheSIG's.The student mayequatetheformation of aloopsealto stopping anyflowthroughtheleg.Page58 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.24 Tier_1_Group L KIA 074 EK3.07 InadequateCoreCooling:

Knowledgeofthereasonsforthe following responsesastheyapplytothe InadequateCoreCooling,Startingup emergency feedwaterandRCP's Importance Rating: 4.0/4.4 Technical

Reference:

FR-C.1Step21startsRCP's.EPM-3-FR-C.1forstep21.

Proposed referencestobe provided to applicants during examination:

None Learning Objective:OPL271FR-C.1B.4 Question Source: Bank#X---ModifiedBank#

---

New-----QuestionHistory:SQNNRCEXAM 1/2008,SQNBankSQNFR-C.1002QuestionCognitive Level: Memory or fundamental knowledge__X_Comprehension or Analysis_10CFRPart55 Content:(CFR41.5 I 41.10 I 45.6/45.13)

Comments: Some distracters changedPage59 1/2008 SequoyahSRONRCExam 02/08/2008 25.Given the following:-Theunithasbeenat1 00%power-Total primary to secondary leakageis29gpd-Identified RCS leakageis0.02gpm-Unidentified RCS leakageis0.02 gpm-Pzrlevel, VCT level, chargingflow,and letdown flowareall stableIffuel failure resultedina significant increaseinRCS activity,whichONE(1) of the following identifies how the identified process rad monitors would respond?1-RM-90-106

-Lower Containment Radiation Monitor 1-RM-90-119

-Condenser Vacuum Pump Exhaust Rad Monitor 1-RM-90-106 1-RM-90-119 A.Stable Rising B.Stable StableRising Rising D.Rising StablePage60 1/2008SequoyahSRONRCExam 02/08/2008A.Incorrect,The lower containment radiation monitors will increase concurently with the condenser vacuum pump radiation monitor as described in AOP-R.01.Plausible if the candidate concludesthatthe radiation in lower containment will not increase.B.Incorrect,Both of the radiation monitorswillsee increased radiation as described in AOP-R.01.Plausible if the candidate concludes thatwiththe radiation in lower containment will not increase andthatwiththe identified leakage numbersthatthe condenser vacuum pump would notsensetheincrease.

c.Correct, If a fuel defect occured concurrently with a steam generatortubeleak,the lower containment radiation and the radiation sensedatthe condenser vacuum pump discharge could increase as described in AOP-R.01, Steam Generator Tube Leak.D.Incorrect,The condenser vacuum pump radiation monitor, would notbestable,it would increase as described in AOP-R.01.Plausible because the candidate may concludethatthe radiation in lower containment would rise but also conclude that the condenser vacuum pump would not sense the increase because of the amount of leakageinthequestion.Page61 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.25 Tier2Group2 KIA 076AK2.01 High Reactor Coolant Activity: Knowledgeofthe interrelations betweentheHigh Reactor Coolant Activityandthe following:

Process Radiation Monitors.Importance Rating: 2.6/3.0 Technical

Reference:

AOP-R.01, Steam Generator Tube Leakage AOP-R.06,HighRCS Activity Proposed referencestobe provided to applicants during examination:

None Learning Objective:

Question Source: OPL271AOP-R.01 B.6Bank#X---Modified Bank#-----New----QuestionHistory:SQNNRC EXAM-1/200B, SQN question AOP-R.06-B.0 001 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis X10CFRPart55 Content: Comments: 41.5 I 45.5Page62 1/2008SequoyahSRONRCExam 02/08/200826.Giventhe following plant conditions:

-Reactortripoccurredwith subsequentlossofRCPs.

-Operators have implementedES-0.2,"Natural Circulation Cooldown"togotoColdShutdown.-A cooldownrateof25°F/hourhasbeen established.-RCS depressurizationhasbeeninitiated.-RVLIS upperplenumrange-98%.-TheShift Manager has determinedthatcooldownshallproceedas quickly as possibleduetoreducedCSTinventory.WhichONE(1)ofthefollowing correctlystatesthe procedurethatmaximizesthe allowable cooldownratefortheprovided circumstancesandmaximumcooldownrateallowedbythe procedure?A.UseES-0.2,Natural Circulation Cooldown The cooldownlimitis50 0F/hrB.UseES-0.2,Natural Circulation Cooldown The cooldownlimitis100 oF/hrC.UseES-0.3,Natural Circulation CooldownWithSteamVoidsinVessel(with RVLIS)The cooldownlimitis50 0F/hrUseES-0.3,Natural Circulation CooldownWithSteamVoidsinVessel(withRVLIS)The cooldownlimitis100 0F/hrPage63 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect.Plausibleif studentdoesnot remember a transition pointtoES-0.3dueto needforcooldownduetolowCST inventory and cooldownratelimitsforthe procedures.Cooldownlimit of 50 degrees/hristhe normal cooldownlimiton naturalcirculationhowever,ES-0.3 allowsupto'100 degrees/hr B.Incorrect.Plausibleif studentdoes'not remember a transition pointtoES-0.3dueto needforcooldownduetolow CST inventory and cooldownratelimitsforthe procedures.Cooldownlimit of 50 degrees/hristhe normal cooldownlimiton naturalcirculationhowever,ES-0.3 allowsupto100 degrees/hr C.Incorrect.Plausible if student does remember a transition pointtoES-0.3dueto SMdecisionto proceed as quickly as possibledueto aconditionsuch as CST inventory and student does notknowcooldownratelimitES-0.3.

50 degrees/hr is the normal cooldownlimiton natural circulation and ES-0.3 allowsupto100 degrees/hrD.Correct.The SMdecisionto proceed as quickly as possibledueto aconditionsuch as CST inventory requirestransitiontoES-0.3.ES-0.3limits cooldownto100 degrees/hrPage64 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.26 Tier_1_GroupK/A W/E09 EA2.1.Natural CirculationwithSteamVoidinVessel with/withoutRVLIS:Abilityto determine and interpretthefollowingastheyapplytotheNaturalCirculationwithSteamVoidin Vessel with/withoutRVLIS:Facilityconditionandselectionof appropriate procedures during abnormal and emergency operations.ImportanceRating:3.2/3.9 Technical

Reference:

ES-0.2Rev15Step13 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:QuestionSource:OPL271ES-0.3B.4

&5 Bank#__X__ModifiedBank#

---

New-----QuestionHistory:SQNNRCExam1/2008,RewordedfromSQN FR-C.2-B.4.C 001 Question Cognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis X10CFRPart55Content:

Comments:(CFR43.5/45.13)Page65 1/2008 SequoyahSRONRCExam 02/08/2008 27.While performing actions of FR-Z.1,"ResponsetoHigh Containment Pressure", whatstepsare taken to limitthepeak pressurerisein containmentinthe eventofaMainSteamLine Break in containment?A.StartIce Condenser Air Handling Units.B.Dispatch personneltoopen AirReturnFan breakers.C.Throttle all AFW Flowtolessthan25gpmper Steam Generator.Isolate AFW Flowtoany Steam Generator depressurizinginan uncontrolled manner.A.Incorrect.

Plausibledueto concept ofstartingIce Condenser Air Handling Units mayhelpcool containment thus reducing containment pressure.Step 12directsopening of Ice Condenser AHU Breakers sooptionto start Ice Condenser AirHandlingUnitsiswrong.B.Incorrect.

Plausibledueto requirementtocheckone containmentairreturnfanrunning.Sincethereis asteptoopentheIce Condenser AHU Breakers the student maymistakethe openingontheIce Condenser Air Handling Unit Breakers with Containment AirReturnFanbreakers.

C.Incorrect.

Plausibleduetothrottling feedwater would reduce inventorygoinginto containment thus minimizingsteamrelease pressureriseincontainment.Step 10 (If all S/Gs faulted then controlfeedflowto greaterthanor equal to 25gpmtoeachS/Gto prevent dryout).D.Correct.Step 11 Isolatesfeedflowto affected S/G.Thisstep may eliminate mass and energy releasestothecontainment.Page66 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.27 Tier_1_Group L KIA W/E14 EA2.2 High ContainmentPressure:Abilityto determine and interpret the followingastheyapplytotheHigh Containment Pressure: Adherence to appropriate procedures and operationwithinthelimitationsinthefacility'slicenseand amendments.

ImportanceRating:3.3I3.8 Technical

Reference:

FR-Z.1High Containment PressureEPM-3-FR-Z.1Basis DocumentforFR-Z.1 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:OPL271FR-Z.1B.6 Question Source: Bank#__X__ModifiedBank#

---

New-----QuestionHistory:SQNNRCEXAM 1/2008,BraidwoodUnit1,NRCExamgiven7/17/2002.

Question Cognitive Level:Memoryor fundamental knowledge X ComprehensionorAnalysis

_10CFRPart55Content:

Comments:(CFR43.5 I 45.13)Page67 1/2008 SequoyahSRONRCExam 02/08/200828.Giventhe following:-Unit1isat 32°10 power.-*1BStartBus tripsouton differential relay actuation.

WhichONE(1)ofthe following describestheplant response?Reactor tripsduetothelossof powertoRCP#2andRCP#4.

B.Reactor tripsduetothelossof powertoRCP#1andRCP#3.

C.Onlythe1B-B DIG starts and connectstothe1B-B6.9KVSDBd.D.All4 DIGs start but ONLYthe1B-B DIG connectstothe6.9KVSDBd.A.Correct.UVdueto 1aStartBustriponRCP#2 and 4 meets 2 of 4logicfor a reactor trip under 35%'RTP.a.Incorrect.Plausibleif studentdoesnotknow powersuppliestoRCP's 1and3comesthroughStartbus 1Aand student understands Reactorwilltrip under 35%RTP.C.Incorrect.Plausible if studentdoesnot understandtriplogic under 35%RTP.This part is plausibledueto 1astartbusloss of power and student understands loss of powertoSID boardswillstartEDG's.The student maythinkonlythe 1aDIGwouldstartdueto 1 a startbusloss of power and connecttothe 1aSOad.All 4DIGstart,butonly the 1Awould connectwhichisthewrongDIGidentifiedinthedistractor.

1 a startbusfeeds 1 A shutdown boards..0.Incorrect.Plausible if studentdoesnot understandtriplogic under 35%RTP.This part is plausibledueto 1astartbusloss of power and student understands loss of powertoSID boardswillstartEDG's.The student mayknowALLEDG'sstartbutconfusewhichEDGwould connectwiththeShutdownboards.

All 4DIGstart,butonlythe 1Awould connectwhichisthewrongDIG per the answer listed.1astartbusfeeds 1Ashutdownboard.Page68 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.28 Tier L Group_1_KIA003K3.04ReactorCoolantPumpSystem:Knowledgeofthe effectthatalossor malfunction oftheRCPSwillhaveonthefollowing,RPS.

ImportanceRating:3.9 I 4.2 Technical

Reference:

611-99drawings Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPT200.RCPB.4,5 Question Source:Bank#X-----ModifiedBank

1. -----New-----QuestionHistory:SQNNRCExam 1/2008,SONBank RCP-B.10.A QuestionCognitiveLevel:

Memory or fundamental knowledge_ComprehensionorAnalysisX10CFRPart55Content:(CFR41.7 I 45.6)Comments:Changedall distracterstoincreasetheplausibility,Changedinitial powerlevelfrom 30%to32%.Studentmayknowlogicbut misunderstand setpointas30%.Toensure studentknowsthe setpointforpower, power was increased 2%.Page 69 1/2008SequoyahSRONRCExam 02/08/200829.Duringaplant shutdownlcooldown,whichONE(1)ofthefollowing describes the earliest conditionrequiredtoperformHydrogenPeroxide(H 20 2)additiontotheRCSwithoneRCPrunning,andthereasonforthe additionofHydrogenPeroxide?

ConditionA.RCSTempLessThan 250°FprovidedRHRisinserviceB.RCSTempLessThan 250°FprovidedRHRisinserviceC.RCSTempLessThan 180°FRCSTempLessThan 180°F ReasonLowerthe corrosionrateoftheRCS MinimizeDoseinSteam Generator area Lower the corrosionrateofthe ReSMinimizeDoseinSteam Generator areaA.Incorrect.

Plausibleduetothe DissolvedOxygenTechnical requirementlimitnot being applicable below 250 degrees andtheaddition of HydrogenPeroxideoccurs afterRHRisinservice.Sinceadding HydrogenPeroxidewillchange ph, student may may Interpret this as affectingthecorrosionrate.Corrosionrateis affected for a short time by actuallyraisingtheratedueto higheroxygenlevelsinRCS and ph change.B.Incorrect.

Plausibleduetothe DissolvedOxygenTechnical requirementlimitnot being applicable below 250 degrees andtheaddition of HydrogenPeroxideoccurs afterRHRisinservice.MinimizingDoseinSteam Generatorareais correct pernotein procedure.

C.Incorrect.Plausibledueto correcttemplisted butreasonincorrect.Sinceadding HydrogenPeroxidewillchange ph, student may may interpret this as affecting thecorrosionrate.Corrosionrateis affected for a short time by actually raisingtheratedueto higheroxygenlevelsinRCS andphchange.D.Correct.Per0-GO-7.Note:

Any temperaturelessthan180Fwithat leastoneRCPrunning.This minimizesthedoseintheSteam Generator area.Page70 x 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.29 Tier--L Group_1_KIA 003 G2.3.10 Reactor Coolant Pump: Abilitytoperform procedurestoreduce excessivelevelsofradiationandguard against personnel exposure.ImportanceRating:2.9I3.3 Technical

Reference:

O-GO-7Section5.5Step8Note.

Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPL271GO-7B.1 Question Source: Bank#-----ModifiedBank#

---

New----Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge X Comprehension or Analysis_10CFRPart55 Content: Comments:(CFR43.4 I 45.10)Page71 1/2008 SequoyahSRONRCExam 02/08/200830.Giventhe following:Unit1at100

%powerLetdowninserviceat75gpm WhichONE(1)ofthefollowingliststwo conditionswhereBOTHwouldresultina decreaseinthe availableNPSHtotheCCPs?(Evaluate each condition separately)

Condition 1A.VCTLevel transmitter, 1-LT-62-130AfailsLowVCTLevel transmitter 1-LT-62-130AfailsHighC.Raising setpoint on 1-TCV-70-192, Letdown Heat Exchanger TCVD.Lowering setpoint on 1-TCV-70-192, Letdown Heat Exchanger TCV Condition 2Lossofairto 1-FCV-62-77,LetdownFlow IsolationLossofairto 1-FCV-62-93, ChargingFlowControlLossofairto 1-FCV-62-118,LetdownDiverttoHUTLCVLossofairto 1-FCV-62-79,MixedBedHighTempBypassPage72 1/2008SequoyahSRONRCExam 02/08/2008A.Incorrect,the level transmitterfailinglowwould result in automatic makeuptotheVCT andcausetheVCT pressuretorisecausinganincreaseinNPSHtotheCCP.Plausible because the candidate may notrealizethatthefailurecausetheauto make-up and howthatwould affect VCT pressure.Condition 2 is correctinthatletdownwouldisolate lowering levelintheVCT.B.Correct,the level transmitterfailinghighwould resultinthedivertvalve openingcausetheVCT pressuretodropcausingan decreaseinNPSHtotheCCP.Loss ofairtotheChargingFlow Controlvalvewillcausethevalvetofailopenthusraisingchargingflowand increasing the head lossthroughthe pipingdueto highervelocity,thus lowering NPSH.C.Incorrect,raisingthe setpointontheletdown heat exchangerTCVwouldcausethe temperatureintheVCTtorisewhiletheVCT pressure remainedunchanged,thus decreasingtheNPSHtotheCCPs.Loss ofairtothe Letdown Divert to HUT LCVcausesthevalvetofailintheVCTposition therefore not affecting VCT levelorNPSHtotheCCPs.Plausible becausethecandidate could get confusedonwhichwaythe changes effect letdown or not knowwhichwaythevalvefailsonloss of air.D.Incorrect, lowering the setpointontheletdown heat exchangerTCVwouldcausetheVCT temperaturetodrop,thusraisingtheNPSHtothe ch,argingpumps.However, Loss ofairtotheMixedBedHighTemp Bypass willcausethevalvetofailinthe bypass position and ha\(e no effectonVCT level or NPSHtothe chargingpump.Plausible becausethecandidatecouldget confusedonwhichwaythechange of the setpoint effects letdownorthe effect ofthefailure oftheMixedBedHighTemp Bypass valve.Page73 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.30 Tier--L Group_1_KIA004K5.26ChemicalandVolumeControl:

Knowledgeofthe operational implicationsofthe following conceptsastheyapplytotheCVCS:

Relationship betweenVCTpressure andNPSHforChargingpumps.

ImportanceRating:3.1/3.2 Technical

Reference:

1-47W611-62-1 1-47W611-62-2 1-47W611-62-3 1-47W611-62-4 1-47W611-70-2 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPT200.CVCS B.4,&5 x Question Source: Bank#----ModifiedBank#

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New-----Question History:NewforSQNNRCEXAM1/2008 QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysisX10CFRPart55Content:(CFR41.5/45.7)

Comments:Page74 1/2008SequoyahSRONRCExam 02/08/200831.Giventhe following plant conditions:

-Reactorpowerisstableat 66%withTaveonprogram-The pressurizerlevelcontrolsystemisin Automatic WhichONE(1)ofthefollowing identifies the pressurizerlevelcontrol setpoint?D.600/0Page75 1/2008 SequoyahSRONRCExam 02/08/2008 Justification:

Candidate shouldrealizethatat 66%powerandTavgon program, the pressurizer level should be 66%of the pressuirzer level span added backtotheZero power level setpoint.66%(60-24.7)+24.7=47.998=48%BecauseTavg determines pressurizer level, another methodthecandidate mightchooseis determinetheTavgchange and then determine pressurizer level change.PerTI-28page 10 with reactor power 66%, Tavg should be between 567and568 degrees F.PerTablein AOP-C.01 AppendixAwithRx power at 66%.Tavg shouldbe567.6 degrees F and pressurizer level shouldbe48%If Tavg calculatedusingdatainTI-28, Attachment 9,%Rx power (Full power Tavg-Zero powerTavg)+Zero power Tavg 66%(578.2-547)+547=

20.592+547=567.592 If Pressurizer level setpoint calculatedusingdatainTI-28, Attachment 9,withTavg change of20.592dividedbytotalTavgchangefrom 0to100%power then multipliedbychangein pressurizer level from 0to100%power and added backtotheminimum pressurizer level (20.592/31.2)(60%-24.7%)

+24.7=47.998=48%A.Incorrect,Plausibleifthe level setpointatzero power is multipliedbythe%power instead ofthechangein pressurizer level (35.3)66%(24.7)+24.7=41.002=41%B.Incorrect,PlausibleifthechangeinTavg (31.2)is used instead ofthechangein pressurizer level (35.3)66%(31.2)+24.7=42.292%=45%C.Correct, 66%(60-24.7)+24.7=47.998=48%D.Incorrect,Plausible ifthechangein pressurizer level from 0to100%power is divided by the%changein power instead of multiplied.35.3/.66=53.485=53%Page76 1/2008 Sequoyah SRONRCExam 02/08/2008 QuestionNo.31 Tier--L Group_1_KIA004A3.08ChemicalandVolumeControl:Abilityto monitor automaticoperationoftheCVCS, including:

Reactor Power Importance Rating: 3.9/3.9 Technical

Reference:

TI-28Rev212Pg10RxPowervsRXTemp.

TI-28, Attachment 9, Effective Date 6/28/07page14AOP-C.01R17, Appendix A, Tavg/TrefandPzrLevelProgramValues Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPT200.PZRLCS B.3.d x Question Source: Bank#----ModifiedBank

1. _New-----QuestionHistory:SEQBank

1. PZRLEVEL7,SQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge_ComprehensionorAnalysisX10CFRPart55Content:(CFR41.7145.5)Comments: Changedwordinginthestemandpowerlevelofthereactor.changevaluein distractorA,BandC.Page77 1/2008SequoyahSRONRCExam 02/08/200832.Unit1is currentlyinMode3withashutdowntoMode5underway.

WhichONE(1)ofthe following correctly identifies the administrative temperaturelimitandthe electrical interlockforopening1-FCV-74-1

&2,RHRLoop4HotLeg Isolation valves in accordance with 0-SO-74-1,ResidualHeatRemovalSystem?A.<235°F administrativelimit,350 psiq electrical.

interlockB.<235°F administrativelimit,380psig electrical interlockC.<350°F administrativelimit,350psig electrical interlock<350°F administrativelimit,380psig electrical interlockPage78 1/2008SequoyahSRONRCExam 02/08/2008GO-7,Rev48LimitationB.TheRCS pressure and temperatureshouldNOTexceed350psigor 235°F whentheRHRsystemisinservice.RCS pressure and temperatueshallNOTexceed380psigor 350°FwhenFCV-74-1

&-2areopen.0-SO-74-1Rev64,Section5.5.1CAUTIONpriortostep6UnitmustbeinMode4

<<350°F)priorto performing the remainderofthis section.RefertoLCO3.5.3NOTEpriortostep10 Pressure interlocks preventFCV-74-1andFCV-74-2frombeing opened until RCS pressureislessthan380psig.Step11unlocksthe breakers and restores powertoFCV-74-1and FCV-74-2 and subsequentstepsopenthevalves.A.Incorrect,The eaministretive temperaturelimitis<350°F and the electrical interlockis380psig.Plausible becauseboththevalueslisted are identified in 0-GO-7 asthevaluesthe temperature and pressure should not exceedwhenRHRisinservice.B.Incorrect,The administrative temperaturelimitis<350°F and the electrical interlockis380 psig., Plausible because the temperature valuelistedis identified in 0-GO-7 asthevaluethe temperature a should not exceedwhenRHRisinservice and the pressure value listedisthe correct value oftheinterlock.

C.Incorrect,The administrative temperaturelimitis<350°F and the electrical interlockis380psig.Plausible because the pressure valuelistedis identified in 0-GO-7 asthevaluethe pressure should not exceedwhenRHRisinservice and the temperaturevaluelistedinthe correct value of the administrative limit.D.Correct,The administrative temperaturelimitis<350°F and the electrical interlockis380psig as identifiedin0-SO-74-1.Page79 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.32Tier2Group1 KIA 005 A4.03ResidualHeatRemoval:Abilityto manually operate and lor monitorinthecontrolroom:

RHR Temperature, PZR HeatersandFlow,and nitrogen.Importance Rating:'I2.7 Technical

Reference:

0-SO-74.1,RESIDUALHEATREMOVALSYSTEM,Rev640-GO-7,Rev48 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPT200.RHRB.4 Question Source: Bank#XModifiedBank

1. -----New-----QuestionHistory:SQNNRCExam 1/2008,SQNBankRHR-B.12.G008 Question Cognitive Level: Memory or fundamental knowledge__X__Comprehension or Analysis_10CFRPart55 Content:(CFR41.7 I45.5to 45.8)Comments:SQNbank questionRHR-B.12.G008-changedthepressurevaluein2distractorsandchangedwordinginthestembutnotenoughtocallmodified.Page80 1/2008SequoyahSRONRCExam 02/08/2008 33.WhichONE(1)ofthefollowing correctly describes the responseoftheEagle-21systemandSSPSif containment sump swapover level criteria ismetwithavalid SafetyInjectionsignalpresent?

Eagle-21 A.bistables de-energize B.bistables de-energize C.bistables energizebistables energize SSPSinputrelays de-energizeinputrelays energizeinputrelays de-energizeinputrelays energizeA.Incorrect,Eagle-21 bistables do notde-energize,andtheSSPSinput relays do notde-energize.Plausible ifthecandidate confusesoris not awarewhichwaythe bistables/relays respond(energizeor de-energize)tothe containment sump swapover levelcriteriabeingmet.

B.Incorrect,Eagle-21 bistables do not de-energize, buttheSSPSinput relays do.notenergize.Plausibleifthecandidate confusesoris notawarewhichwaythe bistables/relays respond(energizeor de-energize)tothe containment sump swapover levelcriteriabeingmet.

C.Incorrect,Eagle-21 bistablesdoenergize, buttheSSPS input relays do notde-energize.Plausible ifthecandidate confusesoris notawarewhichway the bistables/relays respond(energizeorde-energize)tothe containment sump swapover level criteria being met.D.Correct,TheEagle-21 bistableswouldenergizeifthe containment sump swapoverlevelcriteria being met, andSSPSinputs relayswouldenergizetocausethelogic circuitry to actuate the master relayintheSSPSsystem.Page81 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.33 Tier--LGroup1KIA006K1.02 EmergencyCoreCoolingSystem:

Knowledgeofthephysical connections and/or cause-effect relationshipbetweentheECCSandthe followingsystems:ESFAS Importance Rating: 4.3/4.6 Technical

Reference:

FSAR,Section7.2and7.31-47W610-63-3 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPT200.RPS,B.3 OPT200.EAGLE21, B.3 x Question Source: Bank#-----ModifiedBank

1. _New-----Question History:SQNNRCEXAM1/2008SQNBankRPS-B.2002whichhasbeenmodified.

Question Cognitive Level:Memoryor fundamental knowledge X Comprehension or Analysis_10CFRPart55 Content:(CFR41.2to 41.9/45.7to 45.8)Comments:Page82 1/2008SequoyahSRONRCExam 02/08/200834.Giventhefollowing:-Unit1wasoperatingat100

%powerwhenaReactorTripandSafetyInjectionoccurred.

ShortlyafterthetheSIactuationthefollowing conditionswereobserved:

-Annunciator 1-RA-90-59ARXBLDGAREARADMONHIGHRADinalarm.-Radiationrisingon:-RxBldgAccessHatch-Upper, 1-RM-90-59-RxBldgPersonnelLock-Upper, 1-RM-90-60-RxBldgInstrRm-Lower,1-RM-90-61 Additionally the following annunciatorswerenotedasbeinginalarm:

-TS-68-309 PRESSURIZERRELIEFTANKTEMPHIGH-TS-30-31 LOWERCOMPTTEMPHIGH-TS-30-241 LOWERCOMPTMOISTUREHI-LS-63-104 CONTAINMENTSUMPFULL-PS-68-301 PRESSURIZERRELIEFTANKPRESSUREHIGHalarmedandcleared.WhichONE(1)ofthefollowingcouldresultinthese conditions, assuming NO operatoractionwastaken?A.#2sealonRCP#4failedPressurizersafetyvalve,1-68-568,failedopenC.ReactorVesselHeadinnerO-ringfailsD.Reactorheadvent throttle valve, 1-FCV-68-396,failedopenPage83 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,Plausibledueto

1. 1 sealleakoffwouldbe routedtothePRT, but if the#2sealfailedtheflowwould notbetothePRT,itwouldbetothe standpipe.

B.Correct,Lift if the Pressurizer safetyvalvewould pressurize the PRT and rupturetheDisc.Steamand redioective fluid/steam wouldthenbe spread in containment.

C.Incorrect,Plausibleduetoradiationwouldincreaseatthesealtable,This does notrelievetothe PRT and conditions in PRT would not be as stated inthequestionstem.

D.Incorrect,PlausiblebecausetheVentlineis routedtothe PRT failure of 1valveintheventlinewouldnot resultinflowtothe PRTdueto another normally closedvalveinseries.Page84 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.34Tier2Group1 KIA007K3.01 Knowledgeofthe effectthatalossor malfunctionofthePRTSwillhaveonthe following:

Containment ImportanceRating:3.3I3.6 Technical

Reference:

1-47W809-1Rev74,Rev52, 0-AR-M12-ARev51, 1-AR-M6-CRev32, 1-AR-M5-CRev18, 1-AR-M5-A Rev 31', Proposed referencestobe provided to applicants during examination:

None Learning Objective:

OPT200.PZRPCSB.3,B.4.i Question Source: Bank#_X_Modified Bank#----New----QuestionHistory:SQNNRCExam 1/2008, Bank KEWAUNEE 2/2/06 exam Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis_X_10CFRPart55 Content: Comments: 41.-7I45.6Page85 1/2008SequoyahSRONRCExam 02/08/200835.Giventhefollowing:Unit2isoperatingat100

%RTP.6hoursintotheshift annunciator WINDOW"LS-68-300AlB PRESSURIZERRELIEFTANKLEVEL HI-LOW"ALARMSandlocksinon 2-XA-55-5A annunciator panel.-Thelevel indicatoronM-5indicatestheleveltobe72%.

Redundant instrumentationintheAuxControlroomshowsthePRTleveltobe72%.

PRT temperatureandpressureareverifiedtobethesameasatshiftturnover.

WhichONE(1)ofthefollowing identifies th.econditionofthePRTandtherequiredcrewactionsasaresultofthelevelalarm?A.ThePRTlevelalarmisvalid,entryintoAOP-R.05,RCSLeakandLeak Source Identificationisrequired.B.ThePRTlevelalarmisvalid,entryintoAOP-R.05,RCSLeakandLeak Source IdentificationisNOTrequired.C.ThePRTlevelalarmisfalse.

AccordingtoOPDP-1,themaximumtimethatmaintenancehasto correct the conditioncausingtheinvalidalarmis7days,atwhichtimethealarmisrequiredtobe cleared/disabled.

DY-ThePRTlevelalarmisfalse.AccordingtoOPDP-1,themaximumtimethatmaintenancehasto correcttheconditioncausingtheinvalidalarmis72hours,atwhichtimethealarmisrequiredtobe cleared/disabled.Page86 1/2008 Sequoyah SRO NRC Exam 02/08/2008A.Incorrect, Plausibleduetolevelintankisonthehighend but notatthe alarm setpoint and adjusting lowering level to clearalarmis plausibledueto dark board requirements

-.Highalarmdoes notcomeinuntil 88%, actionwouldbe required ifthelevelwashigh.

B.Incorrect,Plausibleduetolevelintankisonthehighend butnotatthe alarm setpoint and performing aleakrateis plausibledueto ReS leakagecouldbegoingintothistank.Highalarmdoes notcomeinuntil 88%, actionwouldbe required ifthelevelwashigh.

C.Incorrect, Plausibleduetohighalarmdoes notcomeinuntil 88%,whicis correct however if alarm condition NOT corrected within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> initiate actions to have alarm cleared/disabled.

This answer states 7 daysvs72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.i.e.,Per OPDP-1 (anuisancealarmisanalarmthat challenges crew communications or performance)sincethisalarmis not a nuisance andthereisno 7 day requirement for nuisance alarms this answerisincorrect.D.Correct,The PRT levelalarmisfalse.TheHighalarmdoes notcomein until88%.PerOPDP-1"Initiate a WO and ifalarmcondition NOT corrected within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> initiate actionstohavealarm cleared/disabled".

Page 87 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.35Tier2Group1 KIA 007G2.1.1 Conduct of Operations Knowledge of conduct of operations requirements.

Importance Rating: Technical

Reference:

3.7/3.8 OPDP-1 2-AR-M5-A Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPL271C209B.23 OPT200.RCS B.4,&5 Question Source: Bank#-----ModifiedBank#

---

NewX--Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge__X__Comprehension or Analysis_10CFRPart55 Content: Comments: 41.10/45.13Page88 1/2008 SequoyahSRONRCExam 02/08/200836.Giventhe following;-BothUnitsin serviceat100%RTP.-C-S Component Cooling Water (CCS)Pumpisin service.WhichONE(1)of the following identifies requirements priorto,andafter, transferringC-SCCSPump power supply manual throwoverswitchto ALTERNATE?B.C.D.Priortothe transferPumpmustbe shutdownPumpmustbe shutdown Alternate feeder supply breakermustbeclosed Alternate feeder supply breakermustbeclosed After the transfer1A-ADG declared INOPERABLE 28-B DG declared INOPERABLE1A-ADG declared INOPERABLE 28-B DG declared INOPERABLEPage89 1/2008 SequoyahSRONRC Exam.02/08/2008A.Correct,Per0-SO-70-1,Pump must be shutdown prior to transfer and the alternate feeder supply breaker mustbeOPEN prior to operating manual throwoverswitch.PerDIG1A-A must be considered INOPERABLE ifTrainA supply breaker is placedinservice per 0-SO-70-1 precautions and limitations.

B.Incorrect,Pump mustbeshutdown.TrainA supply breakerforC-SCCSpumpisno longer tested in 1-SI-OPS-082-026.A.Therefore,load shedding and sequencing functions associatedwithTrainA supply breakerareinoperable.DIG1A-A must be considered INOPERABLE ifTrainA supply breaker is placedinservice per 0-SO-70-1 precautions and limitations.

Plausible because 2B-8isthe normal supply.c.Incorrect,Plausible since transferring to alternate the student maythinkthe Alternate feeder supply needstobeclosed prior to manualtransfer.1A-ADGwouldbe declared INOP as identified in Distractor B.D.Incorrect,Plausiblesince transferring to alternate stude may think Alternate feeder supply needstobeclosed prior to manual transfer.Plausible because 28-Bisthe normal supply.Page90 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.36Tier2Group1KIA008K4.07 KnowledgeofCCWSdesign feature(s) andlor interlock(s) whichprovideforthe following:

OperationoftheCCW swing-bus power supplyandits associated breakers and controls Importance Rating: 2.6/2.7 Technical

Reference:

0-SO-70-1 Component Cooling Water System"B'Train Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPT200CCS B.4.b,c,g Question Source: Bank#----ModifiedBank

1. ----NewX----QuestionHistory:NewforSQNNRCEXAM1/2008 QuestionCognitiveLevel:Memoryor fundamental knowledge__X__Comprehension or Analysis_10CFRPart55Content:

41.7 Comments:Page91 1/2008SequoyahSRONRCExam 02/08/200837.Giventhe following:Unit2was operatingat100%power.-TheLoop1 pressurizersprayvalve controllerfailedcausingthesprayvalveto fully open.WhichONE(1)ofthefollowing describestheresponseofthePZRpressurecontrolsystemtothese conditions?(AssumeNo Operator Actions taken)A.Master controlleroutputwouldINCREASE.

PZR pressurewouldbemaintainedabovethe ReactorTripsetpoint.B.Master controlleroutputwouldINCREASE.

PZR pressure would decreasetothe ReactorTripsetpoint.C.Master controller.outputwouldDECREASE.

PZR pressurewouldbe maintainedabovethe ReactorTripsetpoint.Master controller outputwouldDECREASE.

PZR pressure would decreasetothe ReactorTripsetpoint.Page92 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,The output of the master controller increases as pressure goes high, not as pressure drops belowsetpoint.toturnon heaters not increasing, butwiththe sprayvalvefullyopen,the heaterswouldnotbeabletoterminatethe pressuredrop,and a reactortriponlow pressurizer pressurewouldoccur.Plausibleifthecandidate knowingthatthe heaters should be turned on but confusesthedirection ofthechangeinthe output of the master controller or believesthethe heaters comingonwould prevent the pressure from continuingtodroptothe reactortripsetpoint.B.Incorrect,The output of the master controller increases as pressure goes high, not as pressure drops belowsetpoint.toturnon heaters not increasing, butwiththe sprayvalvefullyopen,the heaters would not beabletoterminatethe pressuredrop,and a reactortriponlow pressurizer pressurewouldoccur.Plausibleifthecandidate knowingthatthe heaters should be turned on but confusesthedirection ofthechangeinthe output of the master controllerandknowsthatthe heaters comingonwould not prevent the pressure from continuingtodroptothe reactortripsetpoint.

C.Incorrect,The output of the master controller does decrease as the pressure drops below setpointtoturnonheaters, butwiththe spray valvefullyopen,the heaters would notbeabletoterminatethe pressure drop, and areactor,triponlow pressurizer pressurewouldoccur.Plausibleifthecandidateknowingthatthe heaters should be turned on andwhichdirection the output of the master controllerwouldchange, but believesthethe heaters comingonwould prevent the pressure from continuingtodropto the reactortripsetpoint.D.Correct,The pressurizer pressurewillbe droppingduetothe spray valvebeingopen.

As the lower pressure is comparedtothe setpoint pressure, the output of the master controllerwillstart droppingtoturnonheaters.Withthe sprayvalvefullyopen,the heaters would notbeabletoterminate the pressure drop, and a reactortriponlow pressurizer pressure would occur.Page93 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.37Tier2Group1KIA010K6.03 Knowledgeofthe effectofalossor malfunctionofthe followingwillhaveonthePZRPCS:PZRspraysand heaters Importance Rating: Technical

Reference:

3.2I3.6 1-,2-27W611-68-3 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

Question Source: OPT200.PZRPCS B.11.a Bank#-----ModifiedBank

1. _X__New-----QuestionHistory:SONNRCExam 1/2008,SQNBankModifiedPZRPRESS-B.11005 Question Cognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis_X_10CFRPart55 Content: Comments:41.7/45.7Page94 1/2008SequoyahSRONRCExam 02/08/200838.Giventhe following eventsandconditions:Unit1was operating at 60%power.Pressurizer pressuredecreasedto1940psig.TheSSPSTrainALow PressurizerPressuretriplogicfailedtoactuate.

WhichONE(1)ofthe following identifythestatusofthetripcoilsonthe reactor tripbreakersRTAandRTBwhenthereactortrips?

A.C.D.RTA 48vUVtripcoil Energized Energized De-energized

De-energized RTB 120v Shunttripcoil De-energized Energized De-energized EnergizedPage95 1/2008 SequoyahSRONRCExam 02/08/2008 As statedinFSAR7.2.1.1...

For a reactor trip, 1)a loss ofDCvoltagetothe undervoltage coil releasesthetrip plunger and 2)the shunttripcoilenergizes, either ofwhichwilltripopenthebreaker.InthisquestiontheTrain B SSPS generates a trip and de-energizesthe"B'reactor trip breaker (RTA)undervoltagecoilandenergizesits shunttripcoil.HowevertheTrainASSPSdoes not generate atrip,therefore,thereactor trip breaker (RTB)undervoltagecoilwill not be de-energized and its shunttripcoilwill notbeenergized.A.Incorrect,the status oftheRTAcoils'iscorrect,thestatus ofRTBcoilsisincorrect,Plausibleifthecandidatedoes reversesthestatus ofthecoilsor incorrectlyidentifieswhichcoilsare normally energized and how theyfunctiontocause a trip.B.Correct,TheTrainASSPSdoes not generate atrip,therefore,the breaker RTA undervoltagecoilwillbe energized and its shunttripcoilwillenergized.TheTrain B SSPS generates a trip de-energizing breaker RTB undervoltage coil andenergizingits shunttripcoil..C.Incorrect,the status oftheRTA andRTBcoilsisincorrect.Plausibleifthe candidate incorrectlyidentifieswhichcoilsare normally energized and howtheyfunctiontocause a trip.D.Incorrect,the status oftheRTAcoilsisincorrect,thestatus ofRTBcoilsiscorrect,Plausible ifthecandidatedoes reversesthestatus ofthecoilsor incorrectlyidentifieswhichcoilsare normally energized and how theyfunctiontocause a trip.Page96 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.38Tier2Group1KIA012K4.04 ReactorProtectionsystem KnowledgeofRPSdesign feature(s) andlor interlock(s)whichprovideforthe following:

RedundancyImportanceRating:3.1I3.3 Technical

Reference:

FSAR7.2.1.1 45N699-1 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.RPS B.5.d&B.4.d xQuestionSource:

Bank#-----ModifiedBank#

---

New-----QuestionHistory:NewforSQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis_X_10CFRPart55 Content:41.7 Comments:Page97 1/2008SequoyahSRONRCExam 02/08/200839.TheUnit1 operatingcrewisrespondingtoa reactortripduetoalossof120VACVital InstrumentPowerBoard 1-1.WhichONE(1)ofthefollowing describestheplantresponseifPZRpressure transmitter 1-PT-68-334 (ChannelII)failed LOWwithno operator action?A.SImasterrelaysonboth trainsofSSPSwouldactuateANDbothtrainsof ECCS equipmentwouldstart.SImasterrelaysonboth trainsofSSPSwouldactuateANDonly"B"train ECCS equipmentwouldstart.C.Onlythe"B"trainSSPSSImasterrelayswouldactuateANDboth trainsofECCS equipmentwouldstart.D.Onlythe"B"trainSSPSSImasterrelayswouldactuateANDonly"B"trainECCS equipmentwouldstart.Page98 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect, MasterRelaysonbothtrainswillhavepower.TrainAfrom ChannelIIIviaan auctioneeringcircuit,however,withthe 1-1ACvital Instrument Power Board deenergized (Channel 1),theslave relays that controltheTrainA equipmentwillnothave a powersupply.Plausible if the candidate mistakesthesource of the power supplyorthinksthatthecircuit that auctioneers powerinthelogiccabinet provides powertotheslave relays.B.Correct, Master Relaysonbothtrainswillhavepower.TrainAfrom ChannelIIIviaan auctioneering circuit,however,withthe 1-1ACvital Instrument Power Boarddeenergized,theslave relays that controltheTrain A equipment will nothavepower.

C.Incorrect, Master Relaysonbothtrainswillhavepower.TrainAfrom ChannelIIIviathe auctioneeringcircuit,however, Channel 1isthe only power supplyfortheslaverelaysthat controltheTrainAequipment.

Plausible ifthecandidate mistakesthesource of the power supplyorthinksthatthecircuitthat auctioneers powerinthelogic cabinet provides power to the slave relays instead of the master relays.D.Incorrect, Master Relaysonbothtrainswillhavepower.TrainAfrom ChannelIIIviaan auctioneering circuit, however, Channel 1isthe only power supplyfortheslave relays that controltheTrainAequipment.

Plausible ifthecandidate mistakesthefunction ofthecircuitthat auctioneers powerinthelogiccabinet.Page99 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.39Tier2Group1 KIA 013K2.01 Knowledgeofbuspower suppliestothefollowing:

ESFAS/safeguards equipment control ImportanceRating:3.6I3.8 Technical

Reference:

47W611-63-1Rev4, AOP-P.03 Rev19, 0-80-99-1 Att1, Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.RPS B.4&5 Question Source: Bank#X----ModifiedBank

1. -----New-----QuestionHistory:SQNNRCExam 1/2008,SQNBank RPS-B.9.A 002 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis_X_10CFRPart55 Content: 41.7 Comments: Bank question RPS-B.9.A002with minor format&wording changePage100 1/2008SequoyahSRONRCExam 02/08/200840.Giventhefollowing:BothUnitsinserviceat100

%RTP.UpperCompartmentCoolingUnitsA-AandB-Bareinserviceonbothunits.Comparetheeffectsofthe inadvertentclosingofthe Lower CompartmentCoolingUnit(LCCU)valveslisted:Unit1,LCCU1A-AERCWInletFCV(Outboard), 1-FCV-67-107Unit2,LCCU2A-AERCWInletFCV(Outboard), 2-FCV-67-107Ifbothofthevalveswereclosed,whichONE(1)ofthefollowing identifiestheeffectontheUpper Containment temperatureonthe respective unit(s)andthe mitigationstrateqy,ifany?A.Upper containment temperaturewouldRISEonUnits1and2.

No additionalcoolingunitwouldbe availabletobeplacedinservicefor either Unit.B.Upper containment temperaturewouldRISEonUnits1and2.

0-80-30-4, Upper CompartmentCoolingUnits,wouldbeusedtoplace additional coolers InserviceonbothUnits.Upper containment temperaturewouldRISEonUnit1only.

No additionalcoolingunitwouldbe availabletobeplacedinserviceforthisUnit.D.Upper containment temperaturewouldRISEonUnit1only.0-SO-30-4,Upper Compartment-CoolingUnits,wouldbeusedtoplace additionalcoolersinserviceforthisUnit.Page101 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,PlausibleduetoU1 temperaturewouldrise butUnit2 temperaturewouldremainconstant.Unit 1 ERCW supplytoUCCUcomesfromthelinetothe LCCU supply but Unit 2 supply is a separate line entering containment.

Additionalcoolingunitsare not available.

B.Incorrect,PlausibleduetoU1 temperaturewouldrise butUnit2 temperature wouldremainconstant.Unit 1 ERCW supplytoUCCUcomesfromthelinetothe LCCU supply but Unit 2 supply is a separate line entering containment.

Additionalcoolingunitsare not available.

C.Correct,Unit 1 only has 2 UCCU and the ERCW is suppliedfromthelinetotheLCCU.Additionalcoolingunitsare not available.D.Incorrect, Plausible becausetheTemprisewouldbeonUnit 1onlybut additionalcoolingunitsare not available.Page102 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.40Tier2Group1KIA022 A2.04Abilityto(a)predictthe impactsofthe following malfunctions or operationsontheCCS;and(b)basedonthose predictions, use procedurestocorrect,control,ormitigatethe consequencesofthose malfunctions or operations:Lossofservice water Importance Rating: 2.9/3.2 Technical

Reference:

0-SO-30-4, Upper CompartmentCoolingUnitsDrawing1 (2)-47W845-3 ERCW Proposed referencestobe provided to applicants during examination:

None Learning Objective:

OPT200.ERCWB.4,5 Question Source:Bank#-----ModifiedBank

1. -----New_X__Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis_X_10CFRPart55Content:

Comments:41.5/43.5/45.3/45.13Page103 1/2008 SequoyahSRONRCExam 02/08/2008 41.WhichONE(1)of the following identifies a provisionofthe containment ice condenser design that increasestheice condenser's abilitytoremoveheat duringasmall break LOCA?A.Meltediceis directedawayfromthe inlet doorsandtoward drain lines by turning vanes.B.Oneoutof everytwoicebayshasa drain which directsmeltedice awayfromthe inlet doors.(Only halfofthetotalhave drains)C¥'Inlet doors have proportioning springs to modulate door opening which equalizes air/steam flow througheachicebay.

D.Intermediate deck doors have proportioning springs to modulate door opening which equalizes air/steam flow througheachicebay.A.Incorrect,Turningvanesdirect air/steam flow notwaterdrainage.Plausible if candidate confused the purpose oftheturningvanes.FromFSARtest results show that containment final peak pressure is not affectedbydrain performance.

B.Incorrect, All ofthebaysdo nothavedrains butmorethan half does.Plausible ifthecandidate believes only half ofthebayshavedrains.FromFSARtest results show that containment final peak pressure is not affectedbydrain performance.

c.Correct,The door panels are providedwithtensionspring mechanisms that produce a smallclosingtorqueonthe door panels astheyopen.Thezeroloadposition ofthespring mechanismsissetsuchthat,withzero differential pressure acrossthedoorpanels,the gasket holds the door slightly open.Thissetting provides assurancethatalldoorswillbeopenslightly,upon removal ofcoldairhead, therefore eliminating significant inlet maldistributionforvery small incidents.D.Incorrect,the springsareontheinletdoors, not the intermediate doors.Plausible because the intermediatedoorsdoopenwhen pressurebuildsupintheice condenser bay.Page104 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.41 Tier 2 Group 1 KIA 025 K5.02 Knowledge of operational implicationsofthe following concepts as they applytotheice condenser system: Heat transfer Importance Rating: 2.6I2.8 Technical

Reference:

FSAR 6.5-pages 35,36,6,7 Proposed referencestobe provided to applicants during examination:

None Learning Objective:

Question Source: OPT200lCE B.1 Bank#-----Modified Bank#X--New----Question History:SQNNRCExam 1/2008, WBN Bank SYS061A.03 004 Question Cognitive Level: Memory or fundamental knowledge_X__Comprehension or Analysis_10CFRPart55 Content: Comments: 41.5 I 45.7Page105 1/2008SequoyahSRONRCExam 02/08/200842.Giventhe following:Unit1has experienced a Reactor TripISafetyInjectionduetoaLOCA.-The operatingcrewis implementing the Emergency Instructions and preparingtoalignthesuctionofthe Containment SprayPumpstothe containment sump.Before 1-FCV-72-23, ContainmentSprayPump1ASuctionFrom ContainmentSump,wouldbeopened,the waterlevelinthe containmentsumpwouldhavetobeatleast

__becauseof_A.8%;the interlock associated with 1-FCV-74-3,RHRPump1ASuction Isolation.B.8%;the interlock associated with 1-FCV-72-22, ContainmentSprayPump1ASuctionFromRWST.11%;the interlock associated with 1-FCV-74-3,RHRPump1ASuction Isolation.

D.11%;the interlock associated with 1-FCV-72-22, Containment SprayPump1A SuctionFromRWST.Page106 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,Plausibledueto 8%isthe levelinthe RWSTthatisone ofthetwoconditionsthatinitiatethe manual transfer of the containment spray pump suction to the containmentsump.1-FCV-74-3,RHRPump1ASuctionIsolation,whichis interlockedwiththe ContainmentsumpsuctiontotheRHRpumps.the automatic swapoverfortheRHRsuctionis11%.

B.Incorrect,Plausibledueto 8%isthe levelinthe RWSTthatisone ofthetwoconditionsthatinitiatethe manual transfer of the containment spray pumpsuctiontothe containmentsump.The containment spray pumpsuctionfrom the RWST is not interlocked with a containmentsumplevel.1-FCV-74-3,RHRPump1ASuctionIsolation,whichis interlockedwiththe ContainmentsumpsuctiontotheRHRpumps.The automatic swapoverfortheRHRsuctionis11%.C.Correct,1-FCV-74-3,RHRPump1ASuctionIsolation,whichis interlockedwiththe ContainmentsumpsuctiontotheRHRpumps.The automatic swapoverfortheRHRsuctionis11%.D.Incorrect,Plausibledueto minimumlevelis correcthowever,the associated interlockiswith opening oftheRHRsuctionvalve.The1-FCV-74-3,RHRPump1ASuctionIsolation,whichis interlockedwiththe ContainmentsumpsuctiontotheRHRpumps.The automatic swapoverfortheRHRsuctionis11%.Page107 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.42Tier2Group1 KIA026K4.07 KnowledgeofCSSdesign featurets) andlor interlock(s)whichprovideforthe foliowing:Adequatelevelin containmentsumpforsuction (interlock)

Importance Rating:3.8I4.1 Technical

Reference:

ES-1.3, Transfertothe Containment Sump 1-47W611-72-1Rev9 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:OPL271ES-1.3B.2 OPT200.CS B.4.g Question Source: Bank#-----ModifiedBank

1. _X_New-----QuestionHistory:SQNNRCExam 1/2008,SQNBankModifiedCSS002.

QuestionCognitiveLevel:Memoryor fundamental knowledge__X__ComprehensionorAnalysis_10CFRPart55 Content: 41.7 Comments:Page108 1/2008SequoyahSRONRCExam 02/08/200843.Giventhe followingplantconditions:Unit1in serviceat100%power.DuetotheNormal feeder breaker to 6.9kVShutdownBoard1B-B inadvertently opening,1B-BDiesel Generatorstartedand energizedtheboard.Onehourlater,the following occurs:-At1405a steamlinebreakoccurs inside containment.

Containmentpressureis3psigandrising.-At1407theCROobservesthat1B-B Containment SprayPumpammeterreads'0'ampsandtheonlylightLITabovethe handswitchistheGREENlight.

WhichONE(1)ofthefollowing describes the currentstatusofthe1B-B ContainmentSprayPumpANDthecorrect operatorresponseorreasonfor current status?A.Pumpshouldberunningbuthasfailedtoautostart.

Immediatelystart1B-B Containment Spray Pump after verifying sequencer hastimedout.B.Pumpshouldberunningbuthasfailedtoautostart.Verify1B-B DIG loading available,thenstart1B-B ContainmentSprayPump.C.Pumpstatusis currently correct.UVXandUVYrelaysare preventingstartofthe1B-B ContainmentSprayPump.Pumpstatusis currently correct.Blackout timerhasNOTtimedouttostartthe1B-B ContainmentSprayPump.Page109 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,The Containment SprayPumphasnotfailedtostart.It should not be runningwiththe statedconditions.Thetimerto start the pumpisactivebuthas nottimedout.Plausible because the 1 B-B Shutdown Board experienced the blackout over an hourearlier,the student maythinktimer should alreadybetimedout,whichwould resultinthe pump starting immediatelywhenthe containment pressure reachedthesetpoint.Starting the pumpcouldcause a overloadonthediesel generator if another pump auto startedatthesametimeasthe manual start.B.Incorrect,the Containment SprayPumphas notfailedtostart.It should not be runningwiththe statedconditions.Thetimerto start the pumpisactivebuthasnottimedout.Plausible because the 1 B-B Shutdown Board experienced the blackout over an hourearlier,the student maythinktimer should alreadybetimedout,whichwould resultinthe pump starting immediatelywhenthe containment pressure reachedthesetpoint.Verifying DIG loading prior to starting the pumpisanactiontaken laterwhenaddingloadsto a board supplied by a diesel generatorbutwiththeconditionsgiventhetime sequencerisstill loadingtheboard.Startingthe pumpcouldcause a overloadonthe diesel generator if anotherpumpauto startedatthesametimeasthe manual start.C.Incorrect,Whilethe Containment Spray Pump should not be running with the statedconditions,thereasonis not because the UVX and UVY relays are preventing the start ofthepump.Theserelayscausetheload shedding of the pumpwhenthe boardvoltageislost.

After the board is reenergized these relays will allow the pump to restartwhenthe blackouttimerhastimedout.The BOX and BOY relays are blocking the automatic start untilthe180 second time delayelapses.Thetimerto start the pumpisactive but has nottimedout.Plausiblethe student may know the UVX and UVY relaysfunctionduring a blackout butconfusethefunction and purpose oftheUVX and UVY relay functionsduringthe blackoutconditionsequence.

D.Correct,The Containment Spray Pump shouldnotbe runningwiththestatedconditions.The loading sequencetimeto start the pumpis180 seconds andwhilesome equipment timers startwhenthe boardvoltageisrestored,the spray pumptimerdoes not startuntilboththevoltageis restored and the containment pressure reaches 2.81psig.Since only 2 minuteshaveelapsed,thetimerto startthepumpisactive but has not timedout.The pump should startwhenthetimersequencewhenreached.Page110 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.43Tier2Group1 KIA 026 G2.4.48 Containment SpraySystem:Abilityto interpretcontrolroom indications to verifythestatusand operationofsystem,and understand how operator actions and directives affectplantandsystem conditions.

ImportanceRating:3.5I3.8 Technical

Reference:

AOP-P.01,Lossof OffsitePower,Rev22Appendix8,1,2-45N765-1R16, ,1,2-45N765-3R22;1,2-45N765-5R14,1,2-45N765-7R16, Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPL271C368,8.4 Question Source: Bank#-----ModifiedBank#X

---New-----QuestionHistory:SONNRCExam 1/2008,SONBankModified CSS-B.10 001 Question Cognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis_X__10CFRPart55 Content: Comments: 43.4/45.12Page111 1/2008 SequoyahSRONRCExam 02/08/200844.Giventhe following:-Unit1is1%power.-The OATC inadvertentlylowerstheSteamDump controller setpoint.WhichONE(1)ofthe following identifies a parameter that requires monitoringforTechSpecLCOentry conditions,ANDifreached,whattherequiredactionwouldbeasstatedintheTech Spec action?Parameter A':'RCSTave<541°FB.RCSTave<541°FC.RCS Pressure<2200psiaD.RCS Pressure<2200psia Tech Spec Action Restore withinitslimit within15min Restore withinitslimitwithin30min Restore withinitslimit within5min Restore withinitslimitwithin1hourA.Correct,TechSpec3.1.1.4 is applicableinthismode.RCSTave requiredtobe.::: 541 degrees andactionistorestorewithin 15 min B.Incorrect,TechSpec 3.1.1.4 is applicableinthismode.RCSTave required to be.::: 541 degrees andactionistorestorewithin 15min.Theactionisincorrect.Plausibleduetothereis a 30 min surveillance requirement if the Tavg-Tref Deviationalarmis not reset.C.Incorrect,TechSpec 3.2.5 is not applicableingiven plant parameters.PlausibleduetoRCS pressurewilldrop as RCS temperaturedropsand5 minutes is plausibleduetoactionfor HIGH RCS pressure at lower modes.D.Incorrect,TechSpec 3.2.5 is not applicableingiven plant parameters.

PlausibleduetoRCS pressurewilldrop as RCS temperature drops and 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />swouldbe correct iftheTechSpecwouldhavebeenapplicable.Page112 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.44Tier2Group1 KIA039A1.05MainandReheatSteamSystem:Abilityto predict andlor monitor changes in parameters (to prevent exceedingdesignlimits) associated with operatingtheMRSScontrols including:RCST-ave ImportanceRating:3.2I3.3 Technical

Reference:

TechSpec 3.1.1.4 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.RCS b.6 Question Source: Bank#----ModifiedBank#

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NewX--QuestionHistory:SQNNRCEXAM 1/2008, Question Cognitive Level: Memory or fundamental knowledge X Comprehension or Analysis_10CFRPart55 Content: Comments: 41.5/45.5Page113 1/2008 SequoyahSRONRCExam 02/08/2008 45.Given the following:

Unit 2 operating at 55%power.-All CBPs and HDTPs in service.Both MFPs in service.IftheMainFeedPump Turbine(MFPT)2Btrips, whichONE(1)of the following identifies the correct status of MFPT 2B Condenser Inlet and Outlet Valves(FCVs) followingthetripboth before any Operator action is taken and after the AOP-S.01,Lossof Normal Feedwater,hasbeen completed?

Before any After AOP Operator Action Completion A.Closed Open B.Closed ClosedOpen Open D.Open ClosedPage114 1/2008 Sequoyah SRO NRC Exam 02/08/2008 If one of the MFPTstrip,the Condenser inlet and outletFCVswill automatically close iftheunitisabove60%.

The AFW pumps will automatically startwhenone MFPTtripsifthe plant isabove80%as statedinTI-28.A.Incorrect,Withthetrip occurringatlessthan60%,the AFW pumps would not be running and the condenservalveswould not automaticallycloseduetothetrip oftheMFPT.Plausible ifthecandidatedoes not correctly recalltheconditionsthatwillcausethe automatic closure of the condenser FCVsorthe AFW start conditions associated with a MFPTtriporthe actions containedinthe AOPforloss of a MFPTatlessthan 77%power.B.Incorrect,Withthetrip occurringatlessthan60%,the AFW pumps would not be running and the condenservalveswould not automaticallycloseduetothetrip oftheMFPT.Plausible ifthecandidatedoes not correctly recalltheconditionsthatwillcausethe automatic closure of the condenser FCVsorthe AFW start conditions associated with a MFPTtriporthe actions containedinthe AOPforloss of a MFPTatlessthan 77%power.C.Correct,withthetrip occurringatlessthan60%,thevalveswouldremain open and the AFW pumpswouldremain off.After completing the AOP thevalveswouldremainopen as the AOPonlydirects ensuringthevalvesare closed if the powerlevelis notlessthan60%.D.Incorrect,withthetrip occurringatlessthan60%,thevalveswouldremain open and the AFW pumpswouldremain off.After completing the AOP thevalveswouldremainopen as the AOP only directs ensuringthevalvesare closedifthe powerlevelis notlessthan60%.Plausible ifthecandidate does not correctly recall the conditionsthatwillcausethe automatic closure of the condenser FCVsorthe AFW start conditions associated with a MFPTtriporthe ectlons containedinthe AOPforloss of a MFPTatlessthan77%

power.Page115 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.45Tier2Group1 KIA 059 A2.07 Abilityto(a)predicttheimpactsofthe following malfunctions or operationsontheMFW;and(b)basedonthose predictions, use procedurestocorrect,control,ormitigatethe consequences of those malfunctions or operations:

TrippingofMFWpump turbine Importance Rating: Technical

Reference:

3.0/3.3AOP-S.01,LossofNormal Feedwater,Rev12TI-28,CurveBookrev212,Att.9 effective date 06-28-2007 1, 2-47W611-2-1Rev8 1, 2-47W611-3-1Rev19 1, 2-47W611-6-1Rev19 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPL271AOP-S.01 B.2 OPT200.COND B.4 x Question Source: Bank#-----ModifiedBank#

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New----Question History:NewforSQNNRCEXAM 1/2008QuestionCognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis_x_10CFRPart55 Content: Comments:41.5/43.5 I 45.3 I 45.13Page116 1/2008SequoyahSRONRCExam 02/08/200846.Giventhe following:Unit1 operatingat100%power.-Amain feedwater transientoccursresultinginseveralalarms.

The Operatornotesthe following:

-TurbineVPLis approximately 68%.-ControlRods insertingat72step/min.MFPT1BSPEED CONTROLLERat100%andpump discharge flow increased.MFPT1A indicates0flow.MFW reg valvesdemandat100

%andS/Glevelsare below setpoint.-SteamDump valves open.WhichONE(1)ofthe following identifiesthestatusofMFP1Aandthepositionofthelow pressure(LP)controlvalvesinthesteam supplytotheMFP1A turbine?A.MFP1Ahas tripped;LPControl valves OPEN.MFP1Ahas tripped;LPControl valves CLOSED.C.MFP1AisNOT trippedbuthasunloaded;LPControl valves OPEN.D.MFP1AisNOT trippedbuthasunloaded;LPControl valves CLOSED.Page117 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,the MFPThastripped andallstopand controlvalveswouldbeclosed.Plausible becausethecandidatecouldconfusetheLP control valve response of the MFPTwiththe control valve response of the AFWP turbine.Onthe AFW PT, iftheturbinetrips,thestopvalvetrips closed but the controlvalvegoesfullopenduetoloss ofoilpressure.

Howeveronthe MFPTbothsets ofvalvesclose.B.Correct,the MFPT has tripped and all controlvalveswouldbeclosed.

C.Incorrect,Thevalveposition limiterwouldbeat near100%unless a runback occurredandthe runbackisinitiated by a MFPT tripping.If theturbineunloaded,bothsets ofvalveswouldbeclosed.Plausible because all other conditions are correctforthe unloading ofthe1AMFP and the candidate couldthinkthatonlytheHP controlvalveswouldbe closedifthe turbine unloaded but did not trip.D.Incorrect,Thevalveposition limiterwouldbeat near100%unless a runback occurred and the runbackisinitiated by a MFPTtripping.Plausible because all otherconditionsare correctforthe unloading ofthe1AMFP and the controlvalveswouldbe closed andthestopvalvesopeniftheturbine unloaded but did nottrip.An event similartothis occurredintheplant.Page118 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.46Tier2Group1 KIA059A4.01 Ability to manually operate and monitorinthecontrolroom:

MFW turbine trip indication Importance Rating: Technical

Reference:

3.1I3.1 AOP-S.01,LossofNormal Feedwater,Rev12;1-47W610-46-3R15 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.MFW B.4.f OPL271AOP-S.01 B.2 Question Source: Bank#-----ModifiedBank

1. x----New----Question History:SQNBankAOP-S.10-B-1006 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis_x_10CFRPart55 Content: Comments:41.7I45.5to45.8Page119 1/2008SequoyahSRONRCExam 02/08/200847.Giventhe following;Unit1 experienced a Reactortripfrom100

%power.The Operatorshavenot operated any controls post-trip.Thecrewcompleted E-O, ReactorTripandSafetyInjection,andhasenteredES-0.1, ReactorTripResponse.

Pressurizerlevelis 25%andslowly decreasing.-AllSteam Generatorlevelsarebetween 12%and 18%narrow range and slowly rising.Steam Generators pressures are approximately990psigand slowly decreasing.Tavgis545°Fand slowly decreasing.RCSpressureis2020psigand slowly decreasing.

WhichONE(1)ofthe followingactionsshouldbethefirst priorityofthecrew in accordancewithES-0.1to address the conditions?

A.Establish Emergency Boration.Throttle Auxiliary Feedwater Flow.C.CloseMSIVsandbypassvalves.D.InitiateSafetyInjectionandReturnto E-O.A.Incorrect, ES-0.1 addresses emergency boration if cooldown dropstolessthan540 degrees making this choice plausible.

B.Correct, ES-O.1 step 3 RNO c directs the throttling of AFW to address the cooldown.C.Incorrect,ES-0.1step 3 RNO c.directs the closing of MSIVs and bypass valves if the cooldown continuesinstep 3 RNO d.making this choice plausible, but this action is after the throttling of AFW flow.D.Incorrect, ES-O.1 step 1 directs the initiation of SI and returntoE-O but only ifSIis actuated.Actuation ofSIis not warrantedforthe stated conditions.

Plausibleforthe candidate to misusethedata trends in stem and conclude thatSIwillbe required.Page120 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.47Tier2Group2K/A061K5.01 Auxiliary/Emergency Feedwater System: Knowledgeofthe operational implications of the following concepts as theyapplytotheAFW:

RelationshipbetweenAFWflowand RCS heat transfer.Importance Rating: Technical

Reference:

3.6/3.9 ES-0.1, Reactor Trip Response Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.AFW B.2OPL271ES-0.1B.4 xQuestionSource:

Bank#ModifiedBank#

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New-----Question History:SQNNRCEXAM1/2008,Millstoneexam 2004 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis__X_10CFRPart55 Content: 41.5/45.7 Comments:SQNBankAFWB.2.A003Page121 1/2008 SequoyahSRONRCExam 02/08/200848.Giventhe following plant conditions:Unit1&2are operating steady-stateat100 0/0.-All systems are normally aligned.-Voltageon6.9kV ShutdownBoard1B-B instantaneously drops to'5400volts.

WhichONE(1)of the following describestheplant response to these conditions?

A':I After 1.25 secondsallDiesel Generatorswillautostart.

B.After 1.25 seconds onlythe1B-BDiesel Generatorwillautostart.

C.After 300 secondsallDiesel Generatorswillautostart.

D.After 300 seconds onlythe1B-BDiesel Generatorwillautostart.A.Correct,Voltage<5520voltswill start the 1.25 second timers andallEDGswillstart.

B.Incorrect,Voltagewouldhavetobe<5520voltsto start the 1.25 second timers.All diesel generators are startedinthiscondition.Plausibleif student believes lowvoltageon 1B-Bwould only start the 1B-Bdiesel.

C.Incorrect,Plausibleduetovoltagelessthan 6451 volts but greaterthan5520voltsfor300 seconds these actionswilloccur.D.Incorrect,Plausibleduetovoltagelessthan 6451 volts but greaterthan5520voltsfor300 seconds these actions will occur and if student believeslowvoltageon 1 B-Bwouldonly start the 1B-Bdiesel.Page122 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.48 Tier 2 Group 1 KIA062K1.02 Knowledgeofthephysical connections andlor cause effect relationships betweentheac distributionsystemandthe following systems: ED/G Importance Rating: Technical

Reference:

4.1I4.4TI-28,Att9,Drawing1-45N724-2,1-45N765-1 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.DG, Obj.B.4.e OPT200.BLKOUT, Obj.B.4.e Question Source: Bank#X__ModifiedBank#

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New-----QuestionHistory:SQNNRCExam 1/2008,SQNExamBank D/G-B.9.A 005 Question Cognitive Level: Memory or fundamental knowledge_X__.Comprehension or Analysis10CFRPart55 Content: 41.2 to 41.9 Comments: Changed third bullet from'Voltageon 6.9 kV Shutdown Board1B-Bis5400 volts'to'Voltageon 6.9kVShutdown Board 1B-B instantaneouslydropsto5400 volts'5400 volts.added"instantaneously dropped to"Page123 1/2008SequoyahSRONRCExam 02/08/200849.Giventhe following:

6.9kv ShutdownBoard1A-AcontrolpowerisbeingsuppliedfromtheBACKUPbusNORMAL feederinsupportofa maintenance activity.WhichONE(1)ofthefollowing identifiesthesourceofthecontrolpowertotheshutdownboardandhowthecontrolpower transfer would occurifthenormalsourcewaslost?

Source of Control PowerA.125vVital Battery Board IB.125vVital BatteryBoardI125vVital BatteryBoardIIID.125vVital BatteryBoardIII Control Power Transfer Manual Automatic Manual Automatic A.Incorrect, Plausibleduetothisisthe power supplyforthe 1 A-A control power when being feedfromthe Backup bus alternate feeder.Correct Transfer method.B.Incorrect, Plausibleduetothisisthe power supplyforthe 1 A-A control power when being feedfromthe Backup bus alternate feeder.Incorrect Transfer method.C.Correct,Thisisthe power supplyforthe 1 A-A control power when being feedfromthe Backup bus normalfeeder.The Control Po-wer Transfer is a Manual Xfer.D.Correct,Thisisthe power supplyforthe 1 A-A control power when being feedfromthe Backup bus normal feeder.Incorrect Transfer method.Page124 1/2008 SequoyahSRONRCExam 02/08/2008 Question No.49'Tier2Group1 KIA063K2.01 Knowledgeofbus power suppliestothe following:MajorDCloads Importance Rating: Technical

Reference:

2.9I3.1 AOP-P.02,Lossof 125VDCVital Battery Board 0-45N703-3 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.DC B.4 OPT200.AC6.9KV B.4.b Question Source: Bank#-----ModifiedBank

1. -----NewX--Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis_X__10CFRPart55 Content:41.7 Comments:Page125 1/2008SequoyahSRONRCExam 02/08/200850.The2A-ADGisrunning.A2A-ADGFuelOil Transfer Pump automaticallystartsduetolevelinoneofthedaytanksandthepumpshaft completely shears.WhichONE(1)ofthefollowing correctly describes the operationofthe2A-ADGFuel Oil Transfer pumps?A.ThesecondFuelOil Transferpumpwillberunningduetolow discharge pressureonthefirstpumpthatstarted.B.ThesecondFuelOil TransferpumpwillberunningONLYifbothdaytanksreachalowlevel.C.ThesecondFuelOil TransferpumpwillNOTberunningandwillnotstartasthetanklevel continuestolower.ThesecondFuelOil TransferpumpwillNOTberunning,butwillstartasits associatedtanklevel continuestolower.A.Incorrect,Plausiblebecausecandidate maythinkthat alowdischarge pressureontherunningpumpwouldbe a start signalforthesecondpump.

B.Incorrect,Plausiblebecausecandidate maythinkbothdaytanks must reach a lowlevelbeforethe secondpumpstarts.

C.Incorrect,Plausiblebecausecandidate maythinkthepumpneedstocycle offforthe alternatortostartthe second pump.D.Correct,Two setpoints(Upperlow,and Lowerlow)ontheFuelOilDayTankforautostart ofFuelOilTransferPumps.The alternator alternateswhichpumpisleadandstartsthelead pumponUpper Lowfirst.The Second pumpwillautostarton the Lower Low setpoint.Page126 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.50Tier2Group1 KIA064K6.08 EDG: Knowledgeofthe effectofalossor malfunctionofthe followingwillhaveonthe ED/Gsystem:FueloilstoragetanksImportanceRating:3.2I3.3 Technical

Reference:

45N771-4 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPT200.DGB.4cand5.d.e xQuestionSource:

Bank#----ModifiedBank#

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New-----QuestionHistory:SQNNRCExam 1/2008,SQNBank D/G-B.10 001QuestionCognitiveLevel:Memoryor fundamental knowledge__X__ComprehensionorAnalysis_10CFRPart55Content:

41.7 I 45.7Comments:rewordedstemand distracters not enough to"Modify"Page127 1/2008 SequoyahSRONRCExam 02/08/2008 51.Given the following plant conditions:BothUnits operatingat100%RTP.-All systemsareinanormal alignment A leak occursintheUnit2LetdownHeat Exchanger.

Assuming no actionbythecrew,whichONE(1)ofthe following describes the effectsonthe CCW System?A':'Radiation Monitor 2-RM-90-123A indication rises.Surge Tank vent valves 1-FCV-70-66 and 2-FCV-70-66 closewhenthe monitor reachestheHIGHrad setpoint.B.Radiation Monitor 2-RM-90-123A indication rises.Surge Tank vent valves 2-FCV-70-66 closeswhenthe monitor reachestheHIGHrad setpoint.The 1-FCV-70-66willremainopen.C.Unit2 Surge Tanklevellowers.The2AandC-SCCSpumpswillboth lose suctionwhenthesurgetank empties.D.Unit2 Surge Tanklevellowers.The2ACCSpumpwilllose suctionwhenthesurge tank empties.A.Correct,Aleakonthe Letdown Heat exchangerduetothe pressure differencesonthefluid mediumswillcauseleakageintotheCCSsystem.BothsurgeTankventswillisolate,if setpoint is reached on any of the radiation monitorsontheCCSsystem.

B.Incorrect,Aleakonthe Letdown Heat exchangerduetothe pressure differencesonthefluid mediumswillcauseleakageintotheCCSsystem.BothsurgeTankventswillisolate,if setpoint is reached on any of the radiation monitorsontheCCSsystem.Plausible if studentthinkstheRad Monitoristrainspecific and onlyclosethe associatedunitsventvalve.

C.Incorrect,Aleakwillcause aleakintotheCCSsystem.Plausible if student believesCCSisat a higher pressure andCCSsurgetank level lowers.D.Incorrect,Aleakwillcause aleakintotheCCSsystem.Plausible if student believesCCSisat a higher pressure andCCSsurgetank level lowers.Page128 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.51Tier2Group1 KIA 073 A1*.01 Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits)associated with operatingthePRMsystem controls including:

Radiation levels Importance Rating: Technical

Reference:

3.2I3.5 0-M-AR12-D 1,2-47W611-70-1 1,2-47W611-70-2 Proposed referencestobe provided to applicants during examination:

None Learning Objective:

OPT200.CCS B.5 Ouestion Source: Bank#X--Modified Bank#----New----QuestionHistory:SQNNRCEXAM 1/2008, modifiedfromV.C SummeerJune2007exam Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis_X__10CFRPart55 Content: Comments: 41.5 I 45.7Page129 1/2008 SequoyahSRONRCExam 02/08/200852.Giventhe following plant conditions and information:

Both Units operatingat100%power All systems aligned normallyIfa large ERCW leak developedatthe inlettothe1A1CCSHeat Exchanger, whichONE(1)ofthe ERCW Headerswouldhave increased,flow,andwhenthe leak was isolated,howwouldthe1Aand2A ERCW header pressures be effected?A.B.C¥'D.Header with Flow Increase 1A 1A 2A 2AEffecton Header PressureBoth1Aand2A header pressures would increase Onlythe1A header pressure would increaseBoth1Aand2A header pressures would increase Onlythe2A header pressure would increasePage130 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,The 1 A ERCW supply header is not the header supplyingtheflowforthe1A1&1A2CCS HeatExchangers,the2A header ERCWisthesupply.However, because the headersarecommonatthe pumpingstation,isolatingtheleakwouldcauseboth1A and 2A header pressurestoincrease.Plausible because the componentwiththeleakis a Unit 1 heat exchanger and standard configurationwouldbefor a Unit 1 water header to supplythecoolingandif sotheflowwouldincreaseinthe 1 A header'andthecandidatecould correctlyrelatethe reduction inflowwhenthe leak is isolated to only effecting pressuresinboththe 1 A and 2A headers.B.Incorrect,The 1 A ERCW supply header is not the header supplyingtheflowforthe1A 1&1A2CCS HeatExchangers,the2A header ERCWisthesupply.Additionally, because the headersarecommonatthe pumpingstation,isolatingtheleakwouldcauseboth1A and 2A header pressurestoincrease.Plausiblebecausethe componentwiththeleakis a Unit 1 heat exchanger and standard configurationwouldbefor a Unit 1 water header to supply the coolingandif sotheflowwouldincreaseinthe1A header and thecendtdete couldrelatethereductioninflowwhentheleakis isolated to only effecting pressureinthe 1 A header and not consider the connectionatthe pumping station.C.Correct.2A ERCW supply headeristhe normal supplyforthe 1 A 1&1A2CCSHeat Exchangers andthe2A 1&2A2CCSHeatExchangers.Isolatingtheleakwouldcauseboth 1 A and 2A header pressurestoincrease because the headers arecommonatthe ERCWPumpingStation.D.Incorrect.2A ERCW supply headeristhe normal supplyforthe1A1&1A2CCSHeat Exchangers andthe2A 1&2A2CCS Heat Exchangers.

However because the headers are commonatthe pumpingstation,isolatingtheleakwouldcauseboth1Aand2A header pressurestoincrease.Plausible becausetheflowwouldincreasein onlythe2A header andthecandidate couldrelatethe reductioninflowwhentheleakis isolated to only effecting pressureinthe2A header and not consider the connectionatthe pumping station.Page131 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.52Tier2Group1 KIA076A2.02Abilityto(a)predicttheimpactsofthefollowing malfunctions or operationsontheSWS;and(b)basedonthosepredictions,use procedurestocorrect,control,ormitigatethe consequences.of those malfunctions or operations:

Service water header pressure ImportanceRating:2.7 I 3.1 Technical

Reference:

0-SO-67-1,EssentialRawCooling Water1,2-47W845-1R47;1,2-47W845-2R93;1,2-47W845-5'R59, Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

Question Source: OPT200ERCW B.3 OPT200ERCW B.4 OPT200ERCW B.5 Question History: Bank#-----ModifiedBank#

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NewX---NewforSQNNRCEXAM 1/2008 QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysisX

__10CFRPart55Content:

Comments: 41.5 I 43.5 I 45/3 I 45/13Page132 1/2008 SequoyahSRONRCExam 02/08/2008 53.Given the following: FCV-67-152istheCCSHX081and 082 outlet valve 1-FCV-67-146istheCCSHX1A1and1A2 outlet valve-2-FCV-67-146istheCCSHX2A1and2A2 outlet valve WhichONE(1)of the following identifies which valve(s)receive(s) an automatic reposition signalasa result of a Unit 1 Safety Injection?

A.C.D.O-FCV-67-152 Yes Yes No No 1-FCV-67-146 Yes No Yes Yes 2-FCV-67-146 No No Yes No All Valves listed are automatically or manually manipulated as requiredbyEA-67-1oranSIsignal,thusplausible.The studentwouldbe required to knowwhichvalvewouldrecievean automatic signalorbe requiredtobe manipulated manually.A.Incorrect.O-FCV-67-152 automatically goestothe 35%openpositionforanSI signal on eitherunit.This ensures adequate flow andCGSsystem backpressure fortheBtrainESF equipmentforthe accident unit.2-FCV-67-146 remainsinit's currentpositionuntil manually realigned as directed by EA-67-1.B.Correct.O-FGV-67-152 automatically goestothe 35%openpositionforanSIsignal on eitherunit.This ensuresadequateflow andGCSsystem backpressurefortheBtrainESF equipmentforthe accident unit.1-FCV-67-146 and 2-FCV-67-146 remainsinit's currentpositionuntil manually realigned as directedbyEA-67-1.

C.Incorrect.O-FGV-67-152 automatically goestothe 35%openpositionforanSI signal on eitherunit.This ensures adequate flow and*CGS system backpressure for theBtrainESF equipmentforthe accident unit.1-FCV-67-146 and 2-FCV-67-146remainintheir currentpositionuntil manually realigned as directedbyEA-67-1.

D.Incorrect.O-FCV-67-152 automaticallygoestothe 35%openpositionforanSI signal on eitherunit.This ensures adequate flow andCGSsystem backpressure fortheBtrainESF equipmentforthe accident unit.1-FCV-67-146 remainsinit's current position until manually realigned as directedbyEA-67-1.Page133 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.53Tier2Group1K/A076A4.02Abilityto manually operate and/ormonitorinthecontrolroom:SWSValvesImportanceRating:

2.6/2.6 Technical

Reference:

EA-67-1 47W845-2 47W611-67-5 47W611-99-3 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:QuestionSource:

OPT200.ERCW B.4 Bank#-----ModifiedBank#X New-----QuestionHistory:SQNNRCEXAM1/2008,SQNBank ERCW-B.9.E 003QuestionCognitiveLevel:Memoryor fundamental knowledge_X__ComprehensionorAnalysis

_10CFRPart55 Content: Comments:41.7/45.5to45.8Page134 1/2008 SequoyahSRONRCExam 02/08/2008 54.WhichONE(1)ofthe following identifiestheair supply header pressureatwhichtheTrainA essentialairvalve, 1-FCV-32-80,AuxCmpsrA-ARxBldgU-1Isol,would automaticallyCLOSEandtheeffectthelossofairto containmentwouldhaveonthe Pressurizer Spray Valve?Header Spray Valve Pressure Position A':'50psig decreasing Fails CLOSED B.50psig decreasingFailsOPEN C.69psig decreasing Fails CLOSED D.69psig decreasingFailsOPENA.Correct; 50 psig decreasing and SprayValvesfailclosed.

B.Incorrect; correct Pressure, Incorrectvalveposition(plausible because manyvalvesdofailopen.)

C.Incorrect; Incorrect pressurePlausibledueto 69psigisthe pressure that a valve closedtoisolate Auxiliaryairfrom Control Air, correctvalveposition D.Incorrect; Incorrectpressure.Plausibledueto 69psigisthe pressure that a valve closedtoisolate Auxiliaryairfrom Control Air), Incorrectvalveposition(plausible because manyvalvesdofailopen.)Page135 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.54Tier2Group1 KIA078K3.01 Knowledgeofthe effectthatalossor malfunctionofthelASwillhaveonthe foliowing:Containmentairsystem.

Importance Rating: Technical

Reference:

3.1I3.4 0-SO-32-2 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

Question Source: OPT200.CSA B.4 Bank#----ModifiedBank#_X

__New-----QuestionHistory:'SQNNRCExam 1/200;8,SQNBankAIR008 Question Cognitive Level:Memoryor fundamental knowledge__x__Comprehension or Analysis_10CFRPart55 Content: Comments: 41.7/45.6Page136 1/2008SequoyahSRONRCExam 02/08/200855.Giventhefollowingplantconditions:Unit2experiencedaManualSafetyInjection(SI).

ContainmentPurgeRadMonitors,2-RM-90-130,wasinhighradalarmbuthasbeenreset.

ContainmentPurgeRadMonitors,2-RM-90-131,hasindicated normal..-ContainmentVentIsolationoccurredonTrainA.

ContainmentVentIsolationdidNOToccuronTrainB.PhaseAhasbeenRESET.SIsignalhasNOTbeenRESET.

WhichONE(1)ofthefollowing describesthestatusofthe Containment Vent Isolation(CVI)system?TheCVI and---------shouldhaveoccurredonAandBTrain;theCVIcanberesetwiththeSIsignalpresent.B.shouldhaveoccurredonAandBTrain;theSIsignalmustberesetbeforetheCVIcanbereset.C.shouldNOThaveoccurredonBTrain;theCVIcanberesetwiththeSIsignalpresent.D.shouldNOThaveoccurredonBTrain;theSIsignalmustberesetbeforetheCVIcanbereset.Page137 1/2008 SequoyahSRONRCExam 02/08/2008 A.Correct, A SI signalwillinitiateCVIonbothtrains.

A resetswitchexiststhat is selfsealingwhichwill allowCVItobe reset with aSIsignalstillpresent.

B.Incorrect,First part correct, should have occurredonbothtrains.

Second partincorrect.Plausible if candidate believessinceanSIsignalinitiates aCVIthattheSI must be cleared before resettingtheCVIcanbe accomplished.

C.Incorrect, Plausibleifcandidatedoes not knowanSIsignalwillinitiateCVIonbothtrains, and concludessinceradiationlevelsdid not gouponthe BTrainRad monitorCVITrain B should nothaveoccurred.D.Incorrect,Plausibletoconcludethatwithradiationlevels normalonthe BTrainRadmonitor,CVITrain B should nothaveoccured.

Second part plausible if candidate concludessinceanSI signalinitiatesisolationsignalsthattheSI must be cleared before resettingtheCVIcanbe accomplished.Page138 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.55 TierGroup 1 KIA103A3.01Abilitytomonitorautomaticoperationofthe containmentsystem,including:

Containmentisolation.ImportanceRating:

3.9/4.2 Technical

Reference:

2-47W611-63-1, 2-47W611-88-1 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:OPT200.RPS,Obj.B.18.b OPT200PISQuestionSource:

Bank#-----ModifiedBank#

__X__New-----QuestionHistory:SQNNRCExam 1/2008,SQNBankRPS-B.9005ModifiedQuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysis

_X__10CFRPart55Content:41.7I45.5 Comments:Page139 1/2008 SequoyahSRONRCExam 02/08/200856.Giventhe following:Unit1in MODE 4 RCS temperature at 240°F Pressurizerlevelin automatic at 25%anda steam bubbleisformed 1-XS-68-339E, LEVEL CONTROL CHANNEL SELECTOR,isin the 335/320 position WhichONE(1)of the following identifies which channel is selected as backup AND whetherornotitisaPost Accident Monitoring (PAM)instrument?A.1-L T-68-339, Pressurizer Level Transmitter Channel IThisisaPAM instrumentB.1-L T-68-339, Pressurizer Level Transmitter Channel I ThisisNOTaPAM instrument1-L T-68-335, Pressurizer Level Transmitter Channel II ThisisaPAM instrumentD.1-L T-68-335, Pressurizer Level Transmitter Channel II This is NOTaPAM instrumentA.Incorrect,1-LT-68-339is aPAMinstrument.Plausibledueto 339 is a channel which could be used for level control but not as backup with conditionsinstem'for selectorswitchpostion.

B.Incorrect,11-LT-68-339is aPAMinstrument.Plausibledueto 339 is a channel which couldbeusedfor level control but not as backup with conditionsinstemfor selectorswitchpostion.

C.Correct, Instrumentfailurewouldisolateletdowncausing pressurizer leveltorise,1-L T-68-335isPAMinstrument.D.Incorrect, Correctforbackup however the instrument is aPAMimstrument.Page140 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.56Tier2Group2 KIA011K6.05 PressurizerLevelControlSystem(PZRLCS)

Knowledgeofthe effectofalossor malfunctiononthe followingwillhaveonthePZRLCS:FunctionofPZRlevel gauges as postaccident monitors Importance Rating: 3.1 I 3.7 Technical

Reference:

Tech Spec3.3.3.7,Print 1-47W611-68-2, 1-47W610-68-5 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.PZRPLC B.4 OPT200.PZRPLC B.6 x Question Source: Bank#_ModifiedBank#

---

New----Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis_X_10CFRPart55 Content: 41.7/45.7 Comments:Page141 1/2008SequoyahSRONRCExam 02/08/2008 57.WhichONE(1)ofthefollowingsetsof NuclearInstrumentswouldlosepowerifVital InstrumentPowerBoard 1-11weretobe deenergized?

A':'PowerRangeN42,SourceRangeN32,and IntermediateRangeN36.B.PowerRangeN43,SourceRangeN31,and IntermediateRangeN35.C.PowerRangeN44,SourceRangeN32,and IntermediateRangeN36.D.PowerRangeN41,SourceRangeN31,and IntermediateRangeN35.Thecorrect answerisAA.Correct,120vACVital Instrument Power Board 1-1/isthe power supply forallthree instruments listed.B.Incorrect,N31 andN35are poweredfrom120vACVital Instrument Power Board 1-1.N43is powered from Board 1-1/1.Plausible because N31 and N35 as well as the other listed instrument receive power from a 120v AC Vital Instrument Power Board asdothe instrumentsinthe correct answerandthecandidatecanmistakewhich board supplieswhichinstruments.

C.Incorrect,N44 receives power from a120vACVital Instrument Power Board 1-IV.D.Incorrect,N31 andN35are poweredfrom120vACVital Instrument Power Board 1-1.Page142 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.58 Tier2Group2KIA015K2.01 Knowledge ofbuspower suppliestothe following:

NIS channels,components,and interconnectionsImportanceRating:

Technical

Reference:

3.3/3.7AOP-P.03,LossofUnit1 InstrumentPowerBoard Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:QuestionSource:

OPT200.NIS B.4.b Bank#-----ModifiedBank

1. NISB.4010 New-----QuestionHistory:SQN NRCEXAM1/2008 Question Cognitive Level:Memoryor fundamental knowledge_X__Comprehension or Analysis_10CFRPart55Content:41.7 Comments:Page143 1/2008 SequoyahSRONRCExam 02/08/2008 58.WhichONE(1)ofthe following will occurasaresultof containment pressure increasingto1.54psid?A.CRDM coolers trip Upper compartment coolers tripB.CRDM coolers tripIceCond Floor Cooling Isolation valves isolateC.Incore Instrument Room Chillers trip Upper Compartment Coolers tripIncore Instrument Room Chillers tripIceCond Floor Cooling Isolation valves isolateA.Incorrect,PlausibleduetheCRDMcoolersandUpper compartment coolerswilltripon containment pressure howeverthiswouldrequire containment pressuretoreach 2.81 psid(PhaseB).B.Incorrect,Plausibleduethe CRDMcoolerswilltripon containment pressure howeverthiswouldrequire containment pressuretoreach 2.81 psid (PhaseB).IceCond FloorCoolingIsolationvalveswillisolateon a phaseA(1.54 psid).C.Incorrect,Plausibleduethe Upper compartment coolerswilltripon containment pressure howeverthiswouldrequire containment pressure to reach 2.81 psid(PhaseB).Incore InstrumentRoomChillerswilltripon aphaseA (1.54 psid)D.Correct, Containment pressure of 1.54 psidwillinitiate a Safety Injectionsignal.A Safety Injection Signalwillinitiate a ContainmentIsolationSignalPhaseA.ThePhaseAwilltriptheIncore Instrument room coolerandIce Cond FloorCoolingIsolationvalveswillisolate.Page144 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.58Tier2 Group 2 KIA 016K1.10 Non-Nuclear Instrumentation System:Knowledgeofthephysical connections andlor cause-effect relationships betweentheNNISandthe followingsystems:CCS ImportanceRating:3.1I3.1 Technical

Reference:

1 ,2-47W611-30-2,3,and4.TI-28Att9 1-47W611-88-1 1,2-47W611-61-2 Proposed referencestobe provided to applicants during examination:

None Learning Objective:

Question Source: OPT200.PIS B.4 Bank#-----ModifiedBank#X

---New----QuestionHistory:SONNRCExam 1/2008,ModifiedSONBankCTMT COOL-B.12.A 003 Question Cognitive Level: Memory or fundamental knoyvledge

_X_Comprehension or Analysis_10CFRPart55 Content:41.2to41.9 I45.7to45.8 Comments:Page145 1/2008 SequoyahSRONRCExam 02/08/2008 59.WhichONE(1)of the followingisthe highest core temperaturethatcanbe indicatedbyan Incore Thermocouple while remaininginthe upper indicated physicallimitsin accordancewithGOI-6, Apparatus Operations?A.Incorrect,GOI-6, Rev 121,SectionPidentifiestheindicatingrange of the incore thermocouplestobe200-2300°F.Plausibledueto1200 degrees is aredpathforcorecooling B.Incorrect,GOI-6, Rev 121,SectionPidentifiesthe indicating range of the incore thermocouplestobe200-2300°F.Plausibleduetobeingclosetothe actual temperature of 2300.G.Incorrect,GOI-6, Rev 121,SectionPidentifiestheindicatingrange of the incore thermocouplestobe200-2300°F.Plausibledueto2200isEGCS acceptance criteria.D.Correct,GOI-6, Rev 121,SectionPidentifiestheindicatingrange of the incore thermocouplestobe200-2300°F.Page146 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.59Tier2 Group 2 KIA.017000K4.03 KnowledgeofITMsystemdesign feature(s) andlor interlock(s)whichprovidefor the following:Rangeof temperature indication Importance Rating:3.1/3.3 Technical

Reference:

GOI-6, Apparatus Operation,Rev121,SectionP Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

Question Source: OPL271INCORE, B.4.hBank#X----ModifiedBank

1. -----New-----Question History:SQNNRCExam 1/2008,SQNbank INCORE-B.1.B 003 Question Cognitive Level: Memory or fundamental knowledge_X_Comprehension or Analysis_10CFRPart55 Content: 41.7 Comments:Page147 1/2'008SequoyahSRONRCExam 02/08/200860.WhichONE(1)ofthefollowing identifeshow(a)mainsteam header pressurewillrespondas turbineloadisraisedfrom 50%to 700/0and(b)whichmethod of maintainingTavgmatchedwith TrefwouldresultinthevalueforMTCbeingthe MOST negativeasturbineloadwasraised?A.(a)Mainsteam headerpressurewould decrease.(b)Rodsare withdrawntomaintainTavgonprogram,withBoron concentrationheldconstant.B.(a)Mainsteam headerpressurewouldincrease.(b)Rodsare withdrawntomaintainTavgonprogram,withBoron concentrationheldconstant.

CY'(a)Mainsteam headerpressurewould decrease.(b)Rod positionisheldconstant,whileBoron concentrationisloweredtomaintainTavgonprogram.D.(a)Mainsteam headerpressurewouldincrease.(b)Rod positionisheldconstant,whileBoron concentrationisloweredtomaintainTavgonprogram.Page148 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,First part CorrectMainSteam Header pressure would decrease asturbineloadisraised.Plausibleduetocandidatecould conclude that withdrawingRodswouldmakeMTCmorenegativewhichin reality it makesitLessNegative.

However a competing affect ofTavgrisingwillhave a negative affectonMTC.B.Incorrect,First part IncorrectMainSteam Header pressure would decrease asturbineloadisraised.Plausibleduetocandidatecould conclude that withdrawingRodswouldmakeMTCmore negativewhichin reality it makesitLessNegative.

However a competing affect ofTavgrisingwillhave a negative affectonMTC.C.Correct,First part CorrectMainSteam Header pressure would decrease asturbineloadisraised.

Reduction of boron concentration resultsinmore negativeMTC,Tavgrisingwillhave a negative affectonMTC.Thisadditive Negative affectsisthe MOST negative ofallchoicesgiven.D.Incorrect,First part IncorrectMainSteam Header pressure would decrease asturbineloadisraised.

Reduction of boron concentration resultsinmore negativeMTC,Tavgrisingwillhave a negative affectonMTC.Thisadditive Negative affectsisthe MOST negative ofallchoicesgiven.Page149 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.60Tier2Group2 KIA045K5.17 Knowledgeofthe operational implicationsofthefollowingconceptsastheapplytotheMT/BSystem:Relationshipbetween moderator temperature coefficientandboron concentration in.RCS as TIG load increases Importance Rating: Technical

Reference:

2.5I2.7 NuclearDesignReportUnit1Cycle15 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:GFES CoeficientsQuestionSource:

Bank#-----ModifiedBank#

---

NewX--QuestionHistory:NewforSQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis__X__10CFRPart55Content:

Comments: 41.5/45.7Page150 1/2008SequoyahSRONRCExam 02/08/200861.Giventhefollowing:Unit1isat 60%RTPwithshutdowninprogressduetoSteam Generator#3tubeleakageidentified.-The CondenserVacuumPumpDischargefiltershavebeeninstalled.1-HS-2-255,CONDVACPUMPEXHFILTERBYPASS,isinP-auto.-Aleakonthe condenser vacuum breaker develops leakage equalto30scfm.-Thefollowingalarmsarereceivedat approximatelythesametime:-PDIS-2-255CONDVACPMPSEXHFILTERDIFFPRESSHI. RA-90-99ACNDSVACPMPLORNGAIREXHMONHIGHRAD.WhichONE(1)ofthefollowing identifiesthestatusof 1-FCV-255, CondenserVacuumPumpExhaust FilterBypassFlowControlIsol?Thebypassvalve

_A':'wouldhaveopened AUTOMATICALLYduetothehigh setpointacrossthefilter.B.wouldhaveopened AUTOMATICALLYduetothehighpressure setpointintheexhauststack.C.wouldbepreventedfrom openi*ng AUTOMATICALLYorMANUALLY.D.wouldbepreventedfrom AUTOMATICALLY opening, however valvecouldbeopened MANUALLYusingcontrolswitch.Page151 1/2008 SequoyahSRONRCExam 02/08/2008 A.Correct,WhenCVPdischargefiltertrainisinstalled, FCV-2-255 is designedtoopen automatically on ahighfilterDP of 5.5 in/water increasing.

B.Incorrect,Plausibledueto requirementtoopenthe bypass iftheflowrate exceeds45scfmevenwhenthefiltersare not installed to prevent the instrument malfunction alarmscausebythehigh back pressureinthe exhauststack.Thisis a precautioninthesystem operating instruction.

C.Incorrect, Plausibleduetocandidatecouldthinkthe bypassvalvewouldbe prevented from openingtoensureallrelease gaswentthroughthe monitortoensure releaseismonitored.D.Incorrect, Plausibleduetocandidatecouldthinkthe bypassvalvewould be prevented from opening in automatictoensureallrelease gas wentthroughthemonitor,butwould allow operator controlinmanual.Page152 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.61Tier2Group2 KIA 055 A3.03Abilityto monitor automatic operationoftheCARS, including:

Automatic diversionofCARS exhaust ImportanceRating:2.5 I 2.7 Technical

Reference:

1-AR-M3-A 1-S0-2-9 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200CONDVAC B.4 Question Source: Bank#-----ModifiedBank

1. -----NewX Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis__X_10CFRPart55 Content: Comments: 41.7 I 45.5 Page 153 1/2008SequoyahSRONRCExam 02/08/2008 62.Withthepumpcontrol handswitchesinAUTO,whichONE(1)ofthe following correctly describes operationofthe Reactor Coolant Drain Tank (RCDT)pumpswhen 2-FCV-68-310,PRTDraintoRCDT,isopenedtoreducethelevelinthe Pressurizer ReliefTank(PRT)?A.RCDTPumpAwillautostartONLYifthelevelintheRCDTisabovethelowlevelpump cutofflevelswitch.B.RCDTPumpAwillautostartEVENifthelevelintheRCDTis below thelowlevelpump cutofflevelswitch.C.RCDTPumpBwillautostartONLYifthelevelintheRCDTisabovethelowlevelpump cutofflevelswitch.RCDTPumpBwillautostartEVENifthelevelintheRCDTis below thelowlevelpump cutofflevelswitch.A.Incorrect,TheApumpdoes not receive a startsignalwhen 2-FCV-68-310 is opened, only the B pumphasthis startfunction.Plausible becausethecandidate couldconfusewhich pumpstartswhenthevalveopens andduetothe pump havinganauto start/trip based on RCDTtanklevel.

B.Incorrect,TheA pump does not receive a startsignalwhen 2-FCV-68-310 is opened, only the B pumphasthis startfunction.Plausible becausethecandidate couldconfusewhich pumpstartswhenthevalveopens andduetothe pump havinganauto start/trip based on RCDT tank levelwiththetripbeing bypassed if thevalvewereopen.

C.Incorrect,The B pump will start when 2-FCV-68-310isopened.Thevalveopenlimitswitchinthe startcircuitisin parralleltothe contactthatwouldbeopen if RCDT levelwerelow.Plausible becausethereis a levelswitchthatwouldtripthepumpif the RCDT level decreasedtothe setpoint while pumpingdowntheRCDT,however,thisswitchis bypassed when 2-FCV-68-310isopened.D.Correct,The B pump will start when 2-FCV-68-310isopened.Thevalveopenlimitswitchinthe startcircuitisin parralleltothe contactthatwouldbeopenif RCDT levelwerelow.Page154 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.62Tier2Group2 KIA 068 A4.02 Ability to manually operate andlor monitorinthecontrolroom:

Remote radwaste release Importance Rating: 3.2/3.1'Technical

Reference:

2-S0-68-5, Pressurizer ReliefTank,Rev17 1 ,2-45N779-17Rev21 1 ,2-45N779-45Rev8 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.PZRPCS B.4.OPT200.LRW B.4 QuestionSource:SQNNRCEXAM 1/2008,ModifiedWBBank007A1.01034 Bank#-----ModifiedBank#X

--New----QuestionHistory:NewforSQNNRCExam 1/2008 Question Cognitive Level: Memory or fundamental knowledge__X__Comprehension or Analysis_10CFRPart55 Content: Comments: 41.7 I45.5to45.8Page155 1/2008SequoyahSRONRCExam 02/08/200863.Giventhefollowingplantconditions:GasDecayTank'C'releaseisinprogresswithTrainAABGTSrunningfordilutionflow.IrradiatedFuelassemblyinsertshuffles.arebeingconductedintheSpentFuelPit.

Fuel HandlingAreaExhaustFanAisrunning.-Aleakoccursonthewastegascompressorwhichresultsinagasreleasetothe Auxiliary Building.0-RE-90-101, AuxiliaryBuildingVentMonitor,alarmsduetoHigh radiation. RE-90-102 and 0-RE-90-103,FuelStoragePoolAreaMonitors,indicateNORMALradiationlevelsandareNOTinalarm.WhichONE(1)ofthefollowing indicatestheeffectthiswouldhaveontherunningFuel HandlingAreaExhaustFanandontheABGTS?(Assumeno operatoractionhasbeentaken)A.FuelHandlingAreaExhaustFanwouldremaininservice;TrainBABGTSwouldstart.B.FuelHandlingAreaExhaustFanwouldremaininservice;TrainBABGTSwouldNOTstart.

C.'\i'FuelhandlingAreaExhaustFanwouldbestopped;TrainBABGTSwouldstart.D.FuelhandlingAreaExhaustFanwouldbestopped;TrainBABGTSwouldNOTstart.,Page156 1/2008 SequoyahSRONRCExam 02/08/2008 A.Incorrect-Fuel Handling Area ExhaustFanwillbe stoppedduetoan ABI being initiated andtheTrain B ABGTSwillbe started bytheABI.Plausible because the candidate may concludethatthe Fuel Handling Area Exhaust Fan would not be stoppeddueto normal radiationonthe Spent Fuel Pool Area Monitors.B.Incorrect-Fuel Handling Area ExhaustFanwillbe stoppedduetoan ABI being initiated andtheTrain B ABGTSwillbe started bytheABI.Plausible because the candidate may concludethatthe Fuel Handling Area Exhaust Fans would be stoppedduetoHigh radiationinthe Aux Building stack but thattheTrain B ABGTS would not start becausetheTrain A ABGTS was alreadyinservice.

C.Correct-High radiationinthethe aux building stackwillcausean aux building Isolation resultinginthetripping of the Fuel Handling Area Exhaust Fan and the starting ofbothtrains of ABGTS.D.Incorrect-Fuel Handling area exhaustfanwillbe stoppedduetoan ABI being initiated andtheTrain B ABGTSwillbe started bytheABI.Plausible because the candidate may concludethatthe Fuel Handling Area Exhaust Fans would not be stoppeddueto normal radiationonthe Spent Fuel Pool Area Monitors andthattheTrain B ABGTS would not start becausetheTrain A ABGTS was alreadyinservice.Page157 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.63Tier2Group2 KIA071K3.04 Knowledgeofthe effectthatalossor malfunctionofthe Waste GasDisposalSystemwillhaveonthefollowing:

Ventilation SystemsImportanceRating:

2.7 I 2.9 Technical

Reference:

0-AR-M12-B,CommonRadiation Monitor 0-XA-55-12B, Window B-1 0-SO-30-10, Auxiliary Building VentilationSystems,Rev38 1,2-47W611-30-6 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPT200.ABVENTB.4.g.and i.OPT200.ABGTS B.4.fQuestionSource:

Bank#_ModifiedBank#X

--New-----QuestionHistory:Modified questiononSQN2007exam,SQNNRCEXAM 1/2008QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysis

_X__10CFRPart55 Content: Comments: 41.7/45.6Page158 1/2008SequqyahSRONRCExam 02/08/200864.Giventhe following:Unit1isin service at 70%RTP.-Atubeleakis suspected in Condenser A.1A1and1A3 waterboxesmustbedrainedandtaggedwitha clearance to inspectfora condensertubeleak.-AftertheAmertapsystemisshutdowninautomatic,theAmertapistoberestoredtothe waterboxes on othersideof Condenser A.WhichONEofthe following identifies(1)the requirementfortaggingtheAmertapflowpathsintoandoutofthe1A1and1A3 waterboxes in accordancewithSPP-10.2, Clearance Procedure to Safely Control Energyand(2)howhavingtheCCWinletand outletMOVsclosedoneonesideof CondenserAeffectsthe abilitytooperatea waterboxMOVon Condensers BorCwiththeunitatpower?A.(1)Singlevalve isolationofflowpathis acceptable.(2)AnInletMOVon CondenserBorCcouldNOTbe operated electricallyfromtheMCR,butcouldbe electrically operated locally atthevalve.(1)Singlevalve isolationofflowpathis acceptable.(2)AnInletMOVon CondenserBorCcouldNOTbeoperated electrically neitherfromtheMCRnor locallyatthevalve.C.(1)Twoclosed valvesinseriesisrequiredunlesslackoftwovalve isolation is documented and communicatedtothe clearance holder.(2)AnInletMOVon CondenserBorCcouldNOTbe operated electricallyfromtheMCR,butcouldbe electrically operated locally atthevalve.D.(1)Twoclosed valvesinseriesisrequiredunlesslackoftwovalve isolation is documented and communicatedtothe clearance holder.((2)AnInletMOVon CondenserBorCcouldNOTbe operated electrically neitherfromtheMCRnor locallyatthevalve.Page159 1/2008 Sequoyah SRONRCExam_02/08/2008 The temperature and pressureonthe CondenserCirculatingWatersystemandthe Ammertaptubecleaningsystemislessthanthevaluesrequiringdoublevalveisolationbytheclearance procedure,SPP-10.2,thereforesinglevalveisolationisthe acceptable isolation.

The condenser waterboxMOVsare interlockedsuchthat onlyonesetcan be operated electrically when a CCW pumpisinservice.A.Incorrect,Plausiblebecausethecandidate may correctly identify singleisolationis acceptable butconcludethatthe waterbox MOV could be electrically operated locally.B.Correct,singleflowpathisolationis acceptableforthe clearanceandthe MOVare interlockedsuchthat onlyoneset ofvalvescanbe operated electrically when a CCW pumpisinoperation.

C.Incorrect,Doublevalveisolationis not required and the waterbox MOV could not be operatedlocally.Plausible becausethecandidate may incorrectly determinethatdoubleisolationis required and misapply the interlock configurationonthevalves determiningthatthevalvescouldbe operated locally.D.Incorrect,Doublevalveisolationis notrequired.Plausible because the second part of the answer is correct andthecandidate may incorrectly determine thatdoubleisolationisrequired,while determiningthatthe waterbox MOVs could not be operated electrically.Page160 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.64Tier2Group2 KIA075G 2.2.13 Knowledgeoftaggingand clearance procedures.

Importance Rating: 3.6/3.8 Technical

Reference:

SPP-10.2,Clearance Procedure to SafelyControlEnergy,Rev110-SO-27-1Rev64 1,2-47W611-27-2, Rev 4 Proposed referencestobe provided to applicants during examination:

None Learning Objective:

Question Source:OPL271SPP-10.2B.6 Bank#_ModifiedBank#

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NewX---QuestionHistory:NewforSQNNRCExam 1/2008 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis__X_10CFRPart55 Content: Comments: 41.10/45.13Page161 1/2008SequoyahSRONRCExam 02/08/200865.Giventhe following-The ElectricFirePumpisoutof service for maintainence.-Ascrap lumberfireexistonsitebutnot affectinganyplant equipmentorstructure.-TheFire BrigadeLeadercallstheMCRandrequesttheDieselFirePumpbestarted.

WhichONE(1)ofthefollowing identifies the actionsrequiredbytheMCR operatortostartthedieselfirepumpandtheeffectontheHighPressureFire Protectionsystemifthepumpwereto overspeed afterstartingwiththe overspeed trip mechanism failing to function?The"MCR operatorcouldstartthepumpfromtheMCR.

HPFP headerpressurewould increaseandremainhigh.B.TheMCR operator could NOTstartthepumpfromtheMCR,anAUOwouldhavetostartthepumplocally.

HPFP headerpressurewould increaseandremainhigh.C.TheMCR operatorcouldstartthepumpfromtheMCR.

The pressure would increaseuntilthepump automaticallyshutsdownafteratimedelay.D.TheMCR operator could NOTstartthepumpfromtheMCR,anAUOwouldhavetostartthepumplocally.

The pressure would increaseuntilthepump automaticallyshutsdown afteratimedelay.Page162 1/2008 Sequoyah SRONRCExam 02/08/2008A.Correct,The Operator can startthePumpfromtheMCR.TheDFPhas a reliefvalvethat wi/Iliffonhighpressure.ThePumpdoeshave a timeddelayhigh pressure trip butitis normallynotinservice.The DFP has a reliefvalvethat wi/Iliffonhighpressure.

B.Incorrect,The Operator can startthePumpfromtheMCR.Plausibleifthe student does not know the pumpcanbe startedfromtheMCR.ThePumpdoeshave a timed delay high pressure trip butitis normally notinservice.TheDFPhas a reliefvalvethat wi/Iliffonhigh pressure.C.Incorrect,The Operator can startthePumpfromtheMCR.ThePumpdoes have a timed delay high pressure trip butitis normally notinservice.TheDFPhas a reliefvalvethat wi/Iliffonhighpressure.D.Incorrect,The Operator can startthePumpfromtheMCR.ThePumpdoes have a timed delay high pressure trip butitis normally notinservice.TheDFPhas a reliefvalvethat wi/Iliffonhighpressure.Page163 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.65Tier2Group2 KIA 086A1.01 Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits)associatedwithFire Protection System operatingthecontrols including:

Fire header pressure Importance Rating: Technical

Reference:

2.9/3.3 0-SO-26.2, 1,2-47W850-27 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200HPFP B.3 Question Source: Bank#-----ModifiedBank#

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NewX---Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge__X__Comprehension or Analysis_10CFRPart55 Content: Comments: 41.5/45.5Page164 1/2008 SequoyahSRONRCExam 02/08/2008 66.WhichONE(1)of the following identifiesactions,inthelistbelow, that are includedinthe listing of activities requiredtobe reviewed during Shift Turnover in accordance with OPDP-1, Conduct of Operations,byan on-comingOACat Sequoyah?1.Radiological changes in plant2.PERs generated sincelastshiftworked 3.Standing Orders 4.Temporary Alteration Control forms (TACFs)5.LCOs 6.Priority1and2 Operator WorkaroundsA.All EXCEPT1and2B.All EXCEPT1and4All EXCEPT2and6D.All EXCEPT4and6A.Incorrect, Radiological changes in plant are requiredtobereviewed,PERs ere identifiedonthe Turnover Sheet but are applicableforWBNonly.

B.Incorrect, Radiological changes in plantandTACFsare requiredtobe reviewed.C.Correct, Neither are identifiedasbeing requiredonthe Turnover Sheet.D.Incorrect,TACFsare requiredtobereviewed, Priority 1 and 2 Operator Workarounds are not requiredonthe Turnover Sheet.Page165 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.66Tier3K/A2.1.3 Knowledgeofshift turnover practices Importance Rating: Technical

Reference:

3.0/3.4 OPDP-1 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPL271C209B.10 Question Source: Bank#-----ModifiedBank

1. -----NewX--Question History:NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge__X__ComprehensionorAnalysis

_10CFRPart55 Content:41.10/45.13 Comments:Gotideafromthe Kewaunee 11/15/2004 examPage166 1/2008 SequoyahSRONRCExam 02/08/200867.Giventhe following:Unit2at 35%RTPwith power ascension in progress in accordance with 0-GO-5, Normal Power Operation, following a refueling outaqe.-Aloss of feedwater resultsina reactor trip.-Thelevelinall4 Steam Generators dropsto<0%Narrow Range and starts recovering.

25 seconds afterthetriptheSteam Generator levels are:SG#1-6%SG#2-9%SG#3-40/0SG#4-3%WhichONE(1)of the following identifies the expected responseofthe ATWS Mitigation System Actuation Circuitry(AMSAC)?Arming conditions for AMSACwerenot present.B.AMSAC actuated.C.Arming conditionswerepresent,but actuation conditionswerenot present.D.AMSAchasnot actuated,butwill actuate after the appropriate time delayifSG levels stabilize at their current values.A.Correct,The system does notarmuntilunit poweris>40%and the stated power inquestionis35%.

_B.Incorrect, Levels are belowthesetpoint,however,thesystemdoes notarmuntilunit poweris>40%and the stated powerinquestionis 35%.Plausibleif studentdoesnot know arming setpoint.C.Incorrect,True that AMSAC will notactuate,however,thelevelsarestill below the actuation setpoint (3 out 4<8%).So level recovery is NOTthereasonitdoesnotactuate.Plausible if student does not know 3 out 4<8%logic.'D.Incorrect,Plausible if student remembers a time delay exists and does not know AMSAC is not armedgiventhe current plant conditions of 35%power.Page167 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.67Tier3 KIA G2.1.27 KnowledgeofsystempurposeandorfunctionImportanceRating:

Technical

Reference:

2.8 I 2.9 1.2-47W611-3-5 TI-28 Attachment 9 1-AR-M3-C Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:QuestionSource:QuestionHistory:

Question Cognitive Level: OPT200.AMSAC 8.4 Robinson 9/2004 examSQNNRCEXAM 1/2008Memoryor fundamental knowledge_ComprehensionorAnalysisX

__10CFRPart55Content:

41.7 Comments:Page168 1/2008 SequoyahSRONRCExam 02/08/2008 68.WhichONE(1)ofthefollowingbest describesthefunctionofthe "0" solenoidsinthesteamdumpsystemwhenthe "0" solenoids are energized?

A.Preventsthesteamdumpvalvesfromopeningifthe condenserisnot available.

B.AllowsthesteamdumpcooldownvalvestoopenwhenTavgisbelowtheLo-Lo Tavg interlock.

c.Alignscontrolairto supply for modulationcontrolwhenthesteamdumpsare armed.DY'Allowsthesteamdumpvalvestorespondmore quicklywhenneeded.A.Incorrect, Condenser available interlocks do notinputtothe "0" Solenoids, only the" and"B"solenoids.Plausible because student maycontusewhich solenoids are affected by the condenser available interlocks.

B.Incorrect,Steamdump Bypass interlock feature permits opening cooldown valves belowtheLoLoTavginterlock.This interlock does not not inputtothe"0" solenoids only the and"B" solenoidsfortheCooldownbank.Plausible because student may confuse which solenoids are affectedbytheSteamdump Bypass interlock.

C.Incorrect,0 solenoid aligns controlairfor modulation control when de-energized also, armingsignalsdo not input do notinputtothe "0" Solenoids, only the and"B"solenoids.

D.Correct,"0" solenoids are energizedwhenthereis a large Tavg/Tref deviation indicating a large primary/secondary power mismatch requiring an artificial steamloadonthereactor.Thiscan occur for a rapid turbine loss ofloador reactor trip.energizing "0" solenoids places full control air header pressureonthevalves ratherthanthe modulating control air signal to rapidlyopenthevalvesin 2 stages.Page169 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.68Tier3KIA2.1'.28 Knowledgeofthe purpose and function of major system components and controls.ImportanceRating:3.2 13.3 Technical

Reference:

0-47W611-1-2 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.SDCS B.4.Question Source: Bank#XModifiedBank

1. ----New-----Question History:SQNNRCExam 1/2008,SQNBankMod SDCS-B.7 002 Question Cognitive Level: Memory or fundamental knowledge_X__Comprehension or Analysis_10CFRPart55 Content: 41.7Comments:SQNBankMod SDCS-B.7 002Page170 1/2008 SequoyahSRONRCExam 02/08/200869.Giventhe following:Unit1isinMODE 6withcorereloadinprogress.

LS-78-3, SPENTFUELPITLEVEL HIGH-LOWisinalarmandanAUOhasbeensentto investigate.-SourceRangecounts indicateN31=2cpm,andN32=3cpm.-The17thfuel assemblytobeloadedisintheRefuelMachineMastandisbeingloweredintothecore.

WhichONE(1)ofthefollowing identifies a conditionthatwouldrequirefuelmovementtobe stopped?REFERENCE PROVIDEDA.DuringshiftroundsanAUOreportstheSpentFuelPit Temperaturetobe 69°F.SourceRangecountsduringFuel Assembly insertion indicateN31=4cpm,andN32=7cpm.C.AUOreportsSpentFuelPitlevelisstable approximatelyhalfwaybetweentheEI725.5rungandtheEL726rung.D.TheMCRRO maintainingtheFuel Assembly Transfer Forms (FATF)determinesthatthe18th fuel assemblyisinthePitSide Upender beforethe17th assemblyissetinthecore.Page171 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect, Spent Fuel Pit temperature is analyzeddownto 50 degreesF.Plausible because the candidate mayknowthatthereis a lowerlimiton analyzed temperature but not rememberthevalue ofthelimit.B.Correct, IfbothSRMsincreaseby a factor of 2 during anysingleloadingstep afterthefirst 12 assemblies,fuelloading must stop.c.Incorrect,the levelisslightly belowthelow level alarm butabovetheTS required level.Plausible becausethecandidate may knowthatthereis a lowerlimitonSFP level but not remembertheminimumlevel.D.Incorrect, Fuel assemblies located as statedarewithinthe requirements for assemblies outside of approvedstoragelocations.Plausible becausethecandidate may know thatthereis a maximum number of fuel assembliesthatcanbeoutside approved storage but not remember the actual requirementorconfusethesequence of movement.Page172 1/200-8SequoyahSRONRCExam 02/08/2008 QuestionNo.69Tier3 KIA 2.2.26 Knowledge of refueling administrative requirements.

Importance Rating: 2.5/3.7 Technical

Reference:

FHI-3 MovementofFuel,Rev51 0-SO-78-1, SpentfuelPitCoolingSystem,Rev33 Proposed referencestobeprovidedto applicants during examination:

0-SO-78-1 SpentfuelPitCoolingSystem, Appendix C Learning Objective:

Question Source: Question History: Question Cognitive Level: Comments: OPT200.FH 8.5.a, 8.6.a NewNewforSQNNRCEXAM 1/2008Memoryor fundamental knowledge_Comprehension or Analysis X__Page173 1/2008SequoyahSRONRC Exa.m 02/08/200870.Giventhe following plant conditions:Unit1isat 400/0 power, steady-state, MOLRodcontrolsystemisinMANUAL-Allprocess parametersareonprogram-A malfunctioninthesteamdumpsystemcausesthreesteamdump valvestofail partially open, increasing reactor power to 500/0WhichONE(1)ofthefollowing identifiesthevaluethe Tref would indicateaftertheplant stabilizesANDthespeedatwhichthecontrolrodswouldmoveastheywerebeingwithdrawntorestoreTavg?

A.Tref would indicate approximatelyequaltoControlrodswouldmoveat64 steps/minute.

B.Tref would indicate approximatelyequalto562°F.Controlrodswouldmoveat64 steps/minute.Tref would indicate approximatelyequalto559°F.Controlrodswouldmoveat48 steps/minute.

D.Tref would indicate approximatelyequalto562°F.Controlrodswouldmoveat48 steps/minute.Page174 1/2008 SequoyahSRONRCExam 02/08/2008 Normal Tavg and Tref@40%power=559 0F.Turbineis operatedonIMP OUT sowhendumpsopenthereislittle/nochangeinTrefwhichis basedonturbineloadl.e.turbineimpulse pressure.Therefore, plantwillstabilizeat approximatelsameTref.Normal Manual Rod speed in 48 steps perminute.In Bank select, Manualrodspeedis 48 Steps/minute for control banks and 64 steps/minute for shutdown banks.A.Incorrect,The Trefwouldstabilizeat approximately 559°FwhichistheTreffor40%

power, howevertherod speed in manual is 48 steps perminute.Plausible if the candidate mistakes rod speed in normal manual control with manual rod speed for shutdown banks in banks selectwhichis 64 steps/minute.

B.Incorrect, Tref will notincreaseto 56?OFsinceturbineload tsnotincreasing.

Additional steam load is divertedtosteamdumpsystem.Also, normal manual rodspeedis not 64 steps/minute.Plausibleifthe candidate does notrealizethatTref does notincreaseforthesteamdumpleakand confuses manual shutdown bank rod speed with normal manualrodspeed.C.Correct,Trefwillremainat approximatelythe40%value of 559°Fsinceturbineload is not increasing when additionalsteamloadis divertedtosteamdumpsystem.

Normal manual rod speed is 48 steps/minute.D.Incorrect, Tref will notincreaseto 562°Fsinceturbineloadis not increasing.

Additional steam load is divertedtosteamdumpsystem.Plausible ifthecandidate does notrealizethatTrefdoes notincreaseforthesteamdumpleak but correctly remembers that normal manual control rod speed is 48 Steps/min.Page175 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.70Tier3 KIA G 2.2.33 Equipment Control Knowledgeofcontrolrod programming.

Importance Rating: 3.4/4.0 Technical

Reference:

TI-28,CurveBookAtt.9 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

Question Source: Question History: Question Cognitive Level: OPT200RDCNTB.4.e,B.5.dSQNExamBankmodifiedRDCNTB.4.08SQNNRCEXAM 1/2008Memoryor fundamental knowledge_Comprehension or Analysis X__10CFRPart55 Content: 43.6 Comments:Page176 1/2008SequoyahSRONRCExam 02/08/200871.Giventhe following:Unit2is stable at 3%RTP.-AnRCS samplelinefittinghasasmallleakinsidethePolarCrane Wall.-Aworkplanisbeingpreparedto repairtheleakandtheworkisbeingmergedintotheschedule.WhichONE(1) ofthefollowing identifiesthethelowestlevelofapprovalrequiredtomaketheentryinsidethe'PolarCraneWallatthe current plant conditions?A.Plant ManagerB.SiteVice PresidentRad Protection ManagerD.RadOps Shift SupervisorA.Incorrect, Plant Manager approvalforinside polarcraneis requiredonlyin MODE 1andquestionstemhas plant in MODE 2.B.Incorrect,Site VP approval is not required, however candidatecouldbelieveitisduetobeingat a powerabove0%.C.Correct, Rad Protection Manager approval is required for containment entries outside pre-determined containment building schedule.D.Incorrect, RadOpsShift SupervisorcanwaiveALARAduringemergencies.Page177 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.71Tier3 KIAG2.3.2 Knowledge of facility ALARA program.ImportanceRating:2.5/2.9 Technical

Reference:

RCI-10Rev30 Proposed referencestobe provided to applicants during examination:

None Learning Objective:

Question Source: Question History: Question Cognitive Level:10CFRPart55 Content: Comments:OPL271C260B.9 NewNewforSQNNRCEXAM 1/2008Memoryor fundamental knowledge_ComprehensionorAnalysisX

__41.12/43.4/45.9/45.10Page178 1/2008SequoyahSRONRCExam 02/08/200872.Giventhe following:Unit1isinMode1.

OperatorsareintheprocessofplacingTrainA ContainmentPurgein service to lower containment.

WhichONE(1)ofthefollowing damper(s)isopenedLASTtoensurethatthelowerice doorsremainclosedduringstartupofthepurge?

A.1-FCO-30-1A,PurgeAir SupplyFan1A Suction Isolation Damper1-FCV-30-2,PurgeAir SupplyFan1A Discharge Isolation Damper C.1-FCV-30-61,PurgeAirExhaustFan1A Suction Isolation Damper D.1-FCV-30-213,PurgeAirExhaustFan1A Discharge Isolation DamperA.Incorrect.This damperopenswhenthefansarestarted.Plausible because openingitlastwould providethethesamedip effect as opening the supply discharge damper last.B.Correct.Opening this damperlastisin accordancewiththe procedure.

Need tominimizedip accrossthedoorswhich blowintoopen.C.Incorrect.This mayopenthedoors.Plausible becausethiswouldbethelast damper open if purging upper containment.

D.Incorrect.This mayopenthedoors.Plausible becausethecandidatecouldconfusethis damperwiththe supply fan discharge damper.Page179 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.72 Tier 3KIAG2.3.9Knowledgeoftheprocessforperforminga containment purge.ImportanceRating:

Technical

Reference:

2.5I3.4 0-SO-30-3 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

Question Source: OPT200.CONTPURGE B.5 Bank QuestionHistory:SQNNRCExam 1/2008, CTMT PURGE-B.16.C 001 Question Cognitive Level: Memory or fundamental knowledge_X__Comprehension or Analysis_10CFRPart55Content:43.4/45.10Comments:SQNbankCTMT PURGE-B.16.C001.Changedstemsetupandwording,changedthe original question A distractor, reordered distracters, added damper unique identifiers.

No significant changesPage180 1/2008SequoyahSRONRCExam 02/08/2008 73.Following completionofEA-0-3, Minimizing Secondary Plant Contamination,duringa SGTRevent,whichONE(1)ofthe following identifies the alignmentoftheLowVolume Waste Treatment (LVWT)Pond?A.TheL VWTpondwouldbealignedtothe diffuserpondandalignedtorecievethe discharge of the TurbineBuildingSump.B.TheL VWTpondwouldbealignedtothe diffuserpondbutisolatedfromthe dischargeofthe TurbineBuildingSump.TheL VWTpondwouldbeisolatedfromthe diffuserpondbutaligned'toreclevethe dischargeofthe TurbineBuildingSump..D.TheL VWTpondwouldbeisolatedfromthe diffuserpondandisolatedfromthe dischargeofthe TurbineBuildingSump.A.Incorrect, Procedure does notaligntheLVWT Pondtothe diffuser Pond it isolatestheLVWT pondfromthe diffuser pond.Plausible because the procedure addresses realignment affectingboththeLVWT pond and the diffuser pond and if student assumesTurbineBldgSump discharge may be returnedtothe diffuser pond ifitis realigned to passthroughthe LowVolumeWaste Treatment pond first.B.Incorrect, Proceduredoe'saligntheTurbine Building Sump dischargetothe L VWT pond.Plausible if student assumes turbine building sump discharge must be isolatedfromthe environmentasa result ora SGTR.Also Plausiblesincethe procedure addresses isolation oftheL VWTfromthe Diffuser pond.C.Correct, ProcedurealignsTurbine BuildingSumptotheLVWT pond and isolatestheLVWT Pondfromthe Diffuser pond.D.Incorrect, ProceduredoesalignTurbine Building sump dischargetotheLVWTpond.Plausiblesincethe proceduredoesisolatetheL VWT pondfromthe diffuser pond if student does not remember that if also aligns the Turbine buildingsumptotheL VWT pond or assumesthatturbine building sump discharge must be isolatedfromthe environmentasa result of a SGTR.Page181 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.73Tier3 KIA 2.3.10Abilityto perform procedurestoreduce excessivelevelsofradiationand guard against personnel exposure.Importance Rating: Technical

Reference:

2.9/3.3 EA-0-3 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

Question History: Question Cognitive Level:10CFRPart55 Content: Comments:OPL271E-38.6NewforSQNNRCexam 1/2008Memoryor fundamental knowledge_X__Comprehension or Analysis_43.4/45.10Page182 1/2008SequoyahSRONRCExam 02/08/200874.Giventhefollowing:-Areactortripandsafetyinjectionhasoccurred.

E-O,ReactorTripOrSafetyInjection,isentered.

-WhiletheUnit Supervisor(US)isreadingStep3,anORANGEPath conditiononthe CONTAINMENTCriticalSafetyFunction(CSF)StatusTreeis identifiedbytheSTA.-ThereareNO otherORANGEpath conditions present.WhichONE(1)ofthefollowing identifieswhenthe transitiontotheORANGEPathprocedureistotakeplace:

A.ImmediatelyaftertheUSconfirmstheORANGEPathconditionis present.B.Assoonas verificationthatNOREDPath conditionsexistonremainingstatustrees.C.Assoonasthereadingofthe E-OIMMEDIATEACTIONstepshasbeencompletedbytheUS.When transitionismadefrom E-O and verificationthatNOREDPath condition exist.Page183 1/2008SequoyahSRONRCExam 02/08/2008A.Incorrect,Notransitionhasbeenmadeinthestem ofthequestion,thereforestatustree should not be implemented until atransitionismadefrom E-O or a step is reached in E-Othatdirectsmonitoring.Plausible because Orange paths could be implemented but only after meetingthecriterialistedabovewhichis not met in the stem ofthequestion.

B.Incorrect,Notransitionhasbeenmadeinthestem ofthequestion, thereforestatustree should not be implemented until atransitionismadefrom E-O or a step is reached in E-Othatdirectsmonitoring.Plausible because Orange paths could be implemented afterverificationno REDpathexistswhichwouldtake a higher priority and only aftermeetingthecriterialistedabovewhichis not metinthestem ofthequestion.

C.Incorrect,Notransitionhasbeenmadeinthestem ofthequestion,thereforestatustree should not be implemented until atransitionismadefrom E-O or a step is reached in E-Othatdirectsmonitoring.Plausible because operators are allowedtotake prudent action after immediate actionsstepshavebeencompleted.D.Correct.Notransitionhasbeenmadeinthestem ofthequestion, therefore status tree should not be implemented until atransitionismadefrom E-O or astepis reached in E-O thatdirectsmonitoring.

If no REDpathexitsthenorange paths may be implemented.Page184 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.74Tier3 KIA G 2.4.16 KnowledgeofEOP implementation hierarchy and coordination with other support procedures, Importance Rating: 3.0/4.0 Technical

Reference:

EPM-4,User'sGuide,Revision19 Proposed referencestobe provided to applicants during examination:" None Learning Objective:

Question Source:OPL271EPM-4B.11IndianPoint 2004 QuestionHistory:SONNRCExam 1/2008, Bank Modified Indian Point 2004 Exam Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis__X__10CFRPart 55 Content: Comments: 41.10/43.5/45.13Page185 1/2008SequoyahSRONRCExam 02/08/2008 75.WhichONE(1)ofthefollowing explainstheBASESforthe prioritizationoftheHEAT SINK safety functioncomparedtothe PRESSURIZED THERMAL SHOCK safety function?At;!HEAT SINK safetyfunctionis prioritized HIGHERthanthe PRESSURIZED THERMAL SHOCKsafetyfunction becauseHEATSINKhasa largerimpactonthe barrierstoa fissionproductrelease.B.HEAT SINK safetyfunctionis prioritized HIGHERthanthe PRESSURIZED THERMAL SHOCK safety function becauseHeatSinkmustexistbeforea PRESSURIZED THERMAL SHOCKcouldoccur.C.HEAT SINK safetyfunctionis prioritized LOWERthanthe PRESSURIZED THERMAL SHOCKsafetyfunction becauseaHeatSinkmustexistbeforea PRESSURIZED THERMAL SHOCKcouldoccur.D.HEAT SINK safetyfunctionis prioritized LOWERthanthe PRESSURIZED THERMAL.SHOCK safety function because PRESSURIZED THERMAL SHOCKhasa larger impactonthe barrierstoafission product release.A.Correct.

Per EPM-4HEAT SINK safetyfunctionis prioritized HIGHERthanthe PRESSURIZED THERMAL SHOCK andHEAT SINKhasa Larger impactonthe barriers to a fission product release.B.Incorrect.

Correct prioritization; incorrect Bases.Plausible because student could think thet a heatsinkbe requiredtoinduce a rapid cooldown of the primaryforthe.basis.C.Incorrect.

Incorrect prioritization; Incorrect Bases.Plausible if student does not know prioritization of safety functions and student couldthinkthat a heatsinkbe required to.induce a rapid cooldown of the primaryforthebasis.D.Incorrect.

Incorrect prioritization; correct Bases.Plausible if student does not know prioritization of safety functionsPage186 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.75 Tier 3KIAG2.4.22 Knowledgeofthebasesfor prioritizing safety functions during abnormal/emergency operations.ImportanceRating:3.0/4.0 Technical

Reference:

EPM-3-FR-0 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:OPL271 FR-O B.2 Question Source: Question History: NEWNewforSQNNRCEXAM1/2008 Question Cognitive Level:Memoryor fundamental knowledge_X__Comprehension or Analysis_10CFRPart55Content:CFR:43.5/45.12 Comments:Page187 1/2008 SequoyahSRONRCExam 02/08/2008 76.Given the following:Unit1 experienced a reactor trip I safety injectionduetothe inadvertent opening of a pressurizer safety valve.Reactor CoolantPumpswere stoppeddueto Phase B after verifying Containment Spray in service.Plant conditionswhenthe first Emergency Plan classificationwasmade: Pressurizer pressure1635psigand stable Pressurizer level 1000/0HighQuad.Avg.

Incore Thermocouple572°Fand stable Lowest Tcold544°Fand stable RVLIS 87%and dropping Steam Generator levels 33%NRand stable Highest Containment Radiation1.1E+01 Remlhr and stable Containment Hydrogen 0.00/0 Containment Pressure4.8psidand dropping ContainmentSumpLevel 14%and rising RCS Activity<Tech Spec limit WhichONE(1)ofthe following identifies the required initial Emergency Plan classificationandthe classification required fifty (50)minutes lateriftheHigh Quad.Avg.Incore Thermocoupleis743°FandrisingwithRVLISat48

%?(SED Judgement is NOTtobeusedas criteriaforthe declaration)ReferenceProvided Initial 50 minutes Classification LaterAlertSiteArea Emergency B.Alert General Emergency C..SiteArea EmergencySiteArea Emergency D.Site Area Emergency General EmergencyPage188 1/2008 SequoyahSRONRCExam 02/08/2008A.Correct.Initial conditions result is a loss of 1.2 RCS Barrier EAL 1.2.2RCSLeakage/LOCAdueto subcoolingbeinglessthan 400F and also a potential loss ofthesame1.2.2EAL.NO otherEALcriteriaareapplicable.The 50minuteconditions result the additional Potential Loss of 1.1FuelClad Barrier via 1.1.2, Incore Thermocouple HIQuadAveragewhichcanbe determinedfromthe informationprovided.Additionally, EAL 1.1.1, Critical SafetyFunctionStatus(CoreCoolingOrange)is a Potential Loss of the1.1.1 FuelCladBarrier, butthecandidatewouldhaveto recallthisinformation(theorange pathcriteriais notprovided).Lossor Potential Loss of anytwobarriersresultsinthe declaration being aSiteAreaEmergency.

B.Incorrect.Initial conditions result is a loss of 1.2 RCS Barrier EAL 1.2.2 RCS Leakage/LOCAdueto subcoolingbeinglessthan 400F and also a potential loss ofthesame 1.2.2EAL.NO otherEALcriteriaareapplicable.The General Emergencyclassificationis plausible becausethecandidatecould mistakenly determinefromtheinformationthatcriteriafor InadequateCoreCoolingexist(FR-C.

1REDPath)which would resultintheloss of 1.1FuelClad barrier and the potential loss of 1.3 Containment Barrier(1.3.1-Actions ofFR-C.1ineffectiveduetoCETstendingup)whichwouldbe a GeneralEmergency.Whilethe upward trendexist,theCoreCoolingis NOT aREDPathwiththe statedconditions.CoreCoolingRedPathcriteriawouldhavetobe recalled correctly to preventthiserror.

C.Incorrect.InitialSiteArea Emergency is plausible ifthecandidate misapplies the information provided.The 50minuteclassificationiscorrect.D.Incorrect.InitialSiteArea Emergency and the General Emergency classifications are plausible ifthecandidate misapplies the information provided.Page 189 ,

1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.76 Tier_1_Group_1_KIA008 VaporSpaceLOCA G2.4.41 Knowledgeofthe emergencyactionlevel thresholds and classifications.

ImportanceRating:2.3/4.1 Technical

Reference:

EPIP-1, Emergency Plan ClassificationMatrix,Rev391-FR-0,Unit1 StatusTrees,Rev1 Proposed referencestobeprovidedto applicants during examination:

EPIP-1, Emergency Plan Classification Matrix,pages9and10(Fission Product Barrier Matrix)Learning Objective:

Question Source: OPT271.REP B.3 Bank#-----ModifiedBank#

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NewX----QuestionHistory:SQNNRCExam 1/2008QuestionCognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis_X_10CFRPart55 Content: 10CFR55.43.b (5)Comments:(CFR43.4/45.11)Page190 1/2008SequoyahSRONRCExam 02/08/200877.Giventhe following:Unit1 operating at 100%powerwhenan ATWS occurred following thetripofbothMFPTs.-All S/G waterlevelsare approximately 4%narrowrangeand dropping with ONLYtheMDAFWpump1A-Ain service supplying260gpmto S/G#1and190gpmtoS/G#2.-AtthetimeofentryintoFR-S.1theRCS temperature and pressure are increasing rapidly.Subsequently,whileperfomingFR-S.1,the reactor is successfullytrippedandasafety injectionoccursonlow pressurizer pressure.WhichONE(1)ofthefollowing identifiesBOTHthestatusofthe turbine atthetimeFR-S.1wasenteredandthecorrect procedure implementationasaresultofthe safety injection?

A':I The turbine is tripped.Performsteps1through4of E-O, ReactorTripor SafetyInjection,and ES-0.5, Equipment Verifications, while continuinginFR-S.1.B.The turbine is tripped.Performanceofsteps1 through4of E-O, ReactorTripor Safety Injection,andES-0.5, Equipment Verifications,isNOTpermitteduntilFR-S.1is completed.C.The turbineisNOTtripped.Performsteps1through4of E-O, ReactorTripor SafetyInjection,and ES-0.5, Equipment Verifications, while continuinginFR-S.1.D.The turbineisNOTtripped.

Performanceofsteps1 through4of E-O, ReactorTripor Safety Injection,andES-0.5,EquipmentVerifications,isNOTpermitteduntilFR-S.1is completed.Page191 1/2008 SequoyahSRONRCExam 02/08/2008 A.Correct,Thetrip ofbothMFPsis aturbinetrip signal andtheturbineis tripped as indicatedbytheheatupand pressurization oftheRCS (if theturbinewas nottripped,theRCSwouldbecoolingdown and depressurizing).

Perform steps 1 through 4 of E-O, ReactorTripor Safety Injection, and ES-O.5, EquipmentVerifications,while continuing in FR:"S.1wouldbe correct procedure implementation.B.Incorrect,Thetrip ofbothMFPsis aturbinetrip signal andtheturbineis tripped as indicatedbytheheatupand pressurization oftheRCS (if theturbinewas nottripped,theRCSwouldbecoolingdown and depressurizing).

Procedure implementaionisincorrect.Plausible if student believes no other procdurescanbe implemented while FR-'S.1isin progress.C.Incorrect,Thetrip ofbothMFPsis aturbinetrip signal andtheturbineis tripped as indicatedbythe heatup and pressurization oftheRCS (if theturbinewasnottripped,theRCSwouldbecoolingdown and depressurizing).

Perform steps 1 through 4 of E-O, ReactorTripor SafetyInjection,and ES-O.5, EquipmentVerifications,while continuinginFR-S.1wouldbe correct procedure implementation.D.Incorrect,Thetrip ofbothMFPsis aturbinetrip signal andtheturbineis tripped as indicatedbythe heatup and pressurization oftheRCS (if theturbinewas nottripped,theRCSwouldbecoolingdown and depressurizing).

Procedure implementaionisincorrect.Plausible if student believes no other procdurescanbe implementedwhileFR-S.

1isin progress.Page192 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.77Tier1Group1K/A000029EA2.09 ATWS:Abilitytodetermineor interpretthefollowingasthey applytoaATWS: Occurrenceofamain turbine/reactor trip Importance Rating: 4.4/4.5 Technical

Reference:

FR-S.1, Nuclear Power Generation

'ATWSEPM-3-FR-S.1,Basis DocumentforFR-S.1, Nuclear Power Generation/ATWS FR-O, Status Trees Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:OPL271FR-S.1B5,B7 Question Source: Bank#----ModifiedBank#X

---New-----QuestionHistory:SQNNRCExam1/2008,INPOBank S029EA2.091Robinson 9/27/04QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysis

_X__10CFRPart55Content:

10CFR55.43.b (5)Comments: 43.5/45.13Page193 1/2008SequoyahSRONRCExam 02/08/200878.Giventhe following:Unit1at 4%power,startupinprogressin accordancewithGO-3, Power Ascension from ReactorCriticaltoLessthan5PercentReactor Power.-TheMFWBypassRegvalvesare controlling steam generatorlevelsin AUTO.MainFeedPump(MFP)1Ainservice.MotorDriven Auxiliary FeedwaterPumpshavebeenstoppedandplacedinA-PAUTO.

Following an inadvertent FeedwaterIsolation,thecrewentersAOP-S.01,LossofNormal FeedwaterIfall4SG levelswereat 28%and dropping,whichONE(1)ofthefollowing identifiesthestatus oftheMFWBypassReg Valvesandthe proceduretobeineffectwhentheplantis stabilized?A.MFWBypassRegValveswouldbe closed;AOP-S.01,Loss ofNormalFeedwater.MFWBypassRegValveswouldbeclosed; ES-0.1, Reactor Trip Response.C.MFWBypassRegValveswouldbeopening;AOP-S.01,Loss ofNormalFeedwater.D.MFWBypassRegValveswouldbeopening; ES-O.1, Reactor Trip Response.Page194 1/2008 Sequoyah SRO NRC Exam 02/08/2008A.Incorrect,Thevalveswouldbe closedduetotheFWI,evenwiththe SG levels dropping andBypassregvalve controllers sending signaltoopenthevalves.The AFW pumps would startdueMFP1B having control poweronitstripbusandbeinginthe tripped state resultinginboth MFPTs tripped and the AFW would attempt to control SG levels, however with power levelabovethe capability of AFW,thelevelswouldcontinuetodrop.A reactortripwouldberequired,followingby atransitionto ES-O.1wherethe plantwouldbestabilized.Plausible because the plantwouldbe stabilized in AOP-S.01 if the power level had been lowerinMode 2 and the candidate may not correctly identifythevalves closedbytheFWI signal becausethereis aFWIvalvedownstream.

B.Correct,Thevalveswouldbe closedduetotheFWI,evenwiththe SG levels dropping and Bypassregvalve controllers sending signaltoopenthevalves.The AFW pumps would startdueMFP1B having control poweronitstripbusandbeinginthe tripped state resultinginboth MFPTs tripped and the AFW would attempt to control SG levels, however with power levelabovethe capability of AFW,thelevelswouldcontinuetodrop.A reactortripwouldberequired,followingby atransitionto ES-O.1wherethe plantwouldbestabilized.

C.Incorrect,Dueto SGlevelsdropping, Bypassregvalve controllers would be a sending signaltoopenthevalvesbuttheFWIwouldhavethevalvesclosed.The AFW pumps would startdueMFP 1B having control power onitstripbus andbeinthe tripped state resultinginboth MFPTs trippedwhichstarts AFW pumps.Plausible because the bypassregvalvewould normally be respondingtothelowS/Glevelsby modulating opening.Becausethereis aFWIvalve downstream,thecandidate may not realize the bypassregvalveisalso isolated and because the plantwouldbe stabilized in AOP-S.01 if the power level had been lowerinMode2.D.Incorrect,Dueto SGlevelsdropping, Bypassregvalve controllers would be sending a signaltoopenthevalvesbuttheFWI wouldhavethevalvesclosed.The AFW pumps would startdueMFP 1B having control power onitstripbus andbeinthe tripped state resultinginboth MFPTs trippedwhichstarts AFW pumps.Plausible because the bypassregvalvewould normally be respondingtothe lowS/Glevels by modulating opening.Becausethereis aFWIvalve downstream,thecandidate may not realize the bypassregvalveisalsoisolated.The plantstabilizationinES-O.2is correct.Page195 Question No.Tier1Group11/2008SequoyahSRONRCExam 02/08/2008 78 KIA 054 AA2.05 Ability to determine and interpret the followingasthey applytotheLossofMain Feedwater(MFW):StatusofMFWpumps, regulatingandstopvalves Importance Rating: 3.5/3.7 Technical

Reference:

AOP-S.1,LossofNormal Feedwater Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPT200.MFW B4, OPL271AOP-S.01Question Source: Bank#_ModifiedBank#----NewX--QuestionHistory:NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge_ComprehensionorAnalysis

_X_10CFRPart55 Content: 10CFR55.43.b (5)Comments: 43.5/43.13Page196 1/2008 SequoyahSRONRCExam 02/08/200879.Giventhe following:Unit2is operatingat100%RTPwhena transient causes a reactor trip-The Operating Crew implements E-O, ReactorTripor Safety Injection, then transitionstoES-0.1, Reactor Trip Response, and stabilizes the plant.-The operating crew observes the following:

-Steam dump valves CLOSED.-S/G Atmospheric Relief Valves Operating.FirstOut annunciators DARK.-AllSSPS status lights DARK.WhichONE(1)ofthe following identifies the procedural requirements to place TID AFWpumpin serviceandthe requiredtimetomakethefirst 10CFR50.72 reporttotheNRCin accordance with SPP-3.5?A.Transfer TID AFW Pump Turbine Trip&Throttle valve power supply in accordance with AOP-P.02,Lossof 125vVitalDC Battety Board;4hours.B.Transfer TID AFW Pump Turbine Trip&Throttle valve power supply in accordance with AOP-P.02,Lossof 125vVitalDC Battety Board;8hoursTransfer TID AFW Pump Turbine control power in accordance with AOP-P.04, Loss ofUnit2Vital Instrument Power Board;4hours D.Transfer TID AFW Pump Turbine control power in accordance with AOP-P.04, Loss ofUnit2Vital Instrument Power Board;8hours Page 197 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,the 120vACVital Board 2-1hasfailed as identified bytheStatus light and first out annunciators.

The pump would startdueto having DC power but the speed controllerwouldbe deengerizeduntilthe supply was transferred locally.Plausible if the candidate mistakenlythinksthatthe effectontheTID AFW pumpwouldbe not starting instead of the real effect oftheloss of the speed controlcircuit.ThefirstNRC notification is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report B.Incorrect,the 120v AC Vital Board 2-1hasfailed as identified bytheStatus light and first out annunciators.

The pump would startdueto having DC power but the speed controllerwouldbe deengerizeduntilthe supply was transferredlocally.ThefirstNRC notification is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report.Plausible if the candidate mistakenlythinksthatthe effectontheTID AFW pumpwouldbe not starting instead of the real effect oftheloss of the speed control circuit or misappliestheNRC reporting criteria as many conditions are 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reports.C.Correct,the 120v AC Vital Board 2-1hasfailed as identified by the Status lightandfirst out annunciators.

The pump would startdueto having DC power but the speed controller would be deengerizeduntiltheTID AFW pump power supply was transferredtothe 2-111 boardlocally.Thefirst NRC notification is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report.D.Incorrect,the 120v AC Vital Board 2-1hasfailed as identified by the Status light andfirstout annunciators.

The pump would startdueto having DC power but the speed controllerwouldbe deengerized untiltheTID AFW pump power supply was transferredtothe 2-111 board locally.Plausible if the candidate correctly applies the power supplies transfer needed to restore the speed control circuit but misappliestheNRC reporting criteria.Page198 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.79Tier1Group1 KIA 000057 AA2.17 Ability to determine and interpretthefollowingasthey applytotheLossofVitalAC InstrumentBus:Systemand componentstatus,usinglocalor remote controls ImportanceRating:3.1/3.4 Technical

Reference:

AOP-P.04,LossofUnit2Vital InstrumentPowerBoard Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPL271AOP-P.03

&P.04B2,B6 Question Source:Bank#-----ModifiedBank

1. _NewX--QuestionHistory:NewforSQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis_X__10CFRPart55 Content: 10CFR55.43.b Comments: 43.5/45.13 (5)Page199 1/2008 SequoyahSRONRCExam 02/08/2008 80.Given the following:Unit1isinMODE4 followingaRefuelOutage.

-ABGTSTrainBis tagged for heater bank inspection.

-Annunciator PS-32-104 T-RAINAAUX CONTROL AIR PRESSURELOWalarms.-AUO reports the TrainAAuxairis isolated from station air, Train AAuxAir Compressor runningandthe Train A headeris67psigand slowly dropping.WhichONE(1)ofthe following identifies the actionrequlredperUnit1 Technical Specifications regarding the status of ABGTS?A.ABGTS Train A remains OPERABLEuntilthe Train A Containment Air Isolation valve automatically closes,atwhichtimeLCO3.0.3 entry wouldNOTbe required.B.ABGTS Train A remains OPERABLEuntilthe Train A Containment Air Isolation valve automaticallycloses,atwhichtimeLCO 3.0.3 entry would be required.C.Both ABGTS Trainswouldbe INOPERABLEwiththe current conditions.LCO3.0.3 entry wouldNOTbe required.Both ABGTS Trainswouldbe INOPERABLEwiththe current conditions.

LCO 3.0-.3 entry would be required.Questionrequiresthe knowledge ofwhentheairsystemcan not support the systemsthatrequireair and the application of 2 Technical Specifications for ABGTS.Plant Systems LCO 3.7.8 Auxiliary Building Gas Treatment System and Refueling Operations LCO 3.9.12 Auxiliary Building Gas Treatment System.A.Incorrect, per the ARIforthealarm identifiedinthestem(and AOP-M.2, Loss of Control Air)iftheair pressure is less than 70psigthen controlairis inoperable(anditis not covered by a TIS ofitsown.)The ABGTSisonethe systems affected by the loss ofair.Thus,theTrainA ABGTS must be declaredInoperable.TheTrainA Containment AirIsolationvalve automaticallyclosingis plausibleduetoit occuring at a pressuresettingair on decreasing air pressure.The suspension of tuel movement is a requiredactioninLCO

-3.9.12 if no ABGTStrainis operable making the distractormoreplausible.

B.Incorrect, per the ARIforthe alarm identifiedinthestem(and AOP-M.2,Page200 1/2008SequoyahSRONRCExam 02/08/2008 Loss of Control Air)iftheair pressureislessthan 70psigthen controlairis inoperable(anditis not covered by a TIS ofitsown.)The ABGTSisonethe systems affected bytheloss ofair.Thus,theTrainA ABGTS must be declared Inoperable.TheTrainA Containment AirIsolationvalve automatically closing is plausibleduetoit occurring at a pressuresettingair on decreasing air pressure.The suspension of fuel movement is a requiredactioninLCO

-3.9.12 if no ABGTStrainis operable making the distractor more plausible and the distractoralsohasthe correct application of LCO3.30.3as required by LCO-3.7.8dueto beinginMode4.C.Incorrect,Bothtrains of ABGTS are Inoperable (B-tagged andA-duetolow air pressure as identifiedinthe ARIandin AOP-M.2, Loss of Control Air)Plausible ifthecandidate remembers that LCO-3.0.3 is identifiedasnot being applicableinLCO 3.9.12whichis applicableduetothe movement of irradiatedfuelinthestoragepool, but does not remember LCO 3.7.8isalsoapplicableduetothe plantbeinginMode 4.LCO3.0.3is applicable for not meeting3.7.8 and nothavinganidentifiedaction statementthatcanbe applied.D.Correct,Both trains of ABGTS are Inoperable (B-tagged and A-duetolow air pressure as identifiedinthe ARIandin AOP-M.2, Loss of Control Air)LCO 3.9.12 is applicableduetohaving irradiatedfuelinthepitand requires the movement of irradiatedfuelinthe storage poolbestopped.while notapplicablefor LCO 3.9.12,LCO3.0.3is applicable for not meeting 3.7.8 due to not having an identified action statementthatcanbeapplied.Page201 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.80 Tier1Group1KIA065AA2.01 Ability to determine and interpret the followingasthey applytotheLossof InstrumentAir:Causeand effect of low-pressure instrumentairalarm Importance Rating: 2.9 I 3.2 Technical

Reference:

1-AR-M15-B (A-4)AOP-M.2,LossofControlAir Plant Systems TIS 3.7.8, Auxiliary Building Gas Treatment System Refueling Operations TIS 3.9.12, Auxiliary Building Gas Treatment System 1 ,2-47W611-32-2 Proposed referencestobe provided to applicantsduringexamination:

None Learning Objective:

Question Source: Question History: OPT200.ABGTS B6Bank#-----ModifiedBank#-----NewX----NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis_X_10CFRPart55 Content: 10CFR55.43.b (2)Comments: 43.5/45.13Page202 1/2008SequoyahSRONRCExam 02/08/200881.Giventhe following:Unit2is respondingtoaLOCAwith various Aux Building Radiation Monitorsinalarm.-The operatorsreachthelaststepinthe procedureineffectand observes the following conditions:

RCS pressure1040psigand dropping.RWST WideRangelevel 72%and dropping.ContainmentSumplevelis 00/0.WhichONE(1)ofthefollowing statements identifies

...1)The procedure transitionrequiredtoassure continuedremovalof decay heat under these conditions.

and2)Howthe terminationofECCSflowwouldbe procedurally accomplished when termination criteriawasmet?A':I 1)TransitiontoECA-1.1,LossofRHRSump Recirculation;2)ECCS flowwouldbe terminatedinECA-1.1.B.1)TransitiontoECA-1.1,LossofRHRSump Recirculation;2)ECCS flowwouldbe terminatedinES-1.1.C.1)TransitionbacktoE-1,Lossof Reactor or Secondary Coolant;2)ECCS flowwouldbe terminatedinE-1.D.1)TransitionbacktoE-1,Lossof Reactor or Secondary Coolant;2)ECCS flowwouldbe terminatedinES-1.1Page203 1/2008SequoyahSRONRCExam 02/08/2008A.Gorrect, IfLOGAhas not been isolated as per indicationsgiveninstemthenthe procedure forces aTransitiontoEGA-1.1,Loss ofRHRSump RecirculationandtheSIterminationwouldbe completedinEGA-1.1.B.Incorrect, IfLOGAhas not been isolated as per indicationsgiveninstemthenthe procedure forces aTransitiontoEGA-1.1,Loss ofRHRSump Recirculationhowever,thetheSIterminationwouldbe completed in EGA-1.1notinES-1.

1.Plausible ifthecandidate knowsthetransitionwouldbemadetoEGA-1.

1 but does notknowthattheEGAwillterminatethe safety injection.

G.Incorrect,E-1wouldbethe correcttransitioniftheleak hadbeenisolated.Isolationis determined bytheRGS pressurerisingandthestemstatesthat the pressureisdropping.Plausible ifthecandidatedoes not know the criteria requiredtomakethetransitiontoE-1isRGS pressure increasing.D.Incorrect,E-1wouldbethe correct transition iftheleak had been isolated as determinedbytheRGS pressurerisingandthestemstates that the pressure isdropping.Plausible ifthecandidatedoes not knowthecriteria requiredtomakethetransitiontoE-1isRGS pressure increasing but does knowthatifE-1is entered theSIterminationwouldbe terminatedinES-1.1.Page204 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.81Tier1Group1KIAW/E11 G 2.4.48Abilityto interpretcontrolroom indicationstoverifythestatusandoperationofsystem,and understand how operatoractionsand directives affectplantandsystemconditions.

ImportanceRating:3.5I3.8 Technical

Reference:

ECA-1.2,LOCA Outside Containment Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

Question Source:OPL271ECA-1.2,85 Bank#----ModifiedBank#X

--New----QuestionHistory:SQN N'RC Exam 1/2008,SQNBANKECA-1.2-B.1B001 QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysis

__X_10CFRPart55Content:

10CFR55.43.b (5)43.5 I 45.12Comments:SQNBANKECA-1.2-B.1B001withminorrewordingofthestemto require candidate to determinetheleakisnotisolated(versusstatingtheleakisnotisolatedinthestem)andtocorrect proceduretitlesinthechoicesPage205 1/2008SequoyahSRONRCExam 02/08/200882.Giventhe following:ThecrewisperformingactionsofECA-2.1,"Uncontrolled Depressurization ofAllSteam Generators."TheRCS subcoolingis48 degrees F.RCS pressureis1540psigandrising.

Pressurizerlevelis 24%andrising.

-While performingStep14, MONITOR SI TerminationCriteria,the S/G#4 pressure suddenlybeginstoriseinan uncontrolled manner.Whatactionisrequiredforthis condition?

A.TerminateSIinECA-2.1,then transition to E.-2,FaultedSteam Generator Isolation.

BY'TransitiontoE-2,FaultedSteam GeneratorIsolation,then terminate SI.C.RemaininECA-2.1,SI termination criteriaarenot currently met.D.TransitiontoE-2,FaultedSteam GeneratorIsolation,SI termination criteriaarenot currently met.Page206 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect.ThefoldoutpageEvent Diagnostics and a caution direct the operator nottotransitionuntilSIterminationiscomplete aftertheSIis reset in Step 15.Withterminationcriteria metatstep 14,thecautionandfold out page directionsdo'notapply.The purpose ofthiscautionisto prevent an unnecessarydelayin terminatingSI;thus, prevent/minimize the potential for repressurizing the ReS(PTSconcern).Withthe termination criteria met priortothisstep,the proceduredirectsthetransitiontoE-2whereSIterminationwillbedirected.Plausibleifcandidatedoesnot understand the process to starttheSIterminationprocess.

B.Correct.Thefoldoutpage Event DiagnosticsdirectsthetransitiontoE-2ifSIterminationcriteriais metunlessStep 15throughStep 25areinprogress.

The parameters listed result in meetingSIterminationcriteria.

Meeting the criteria priortoStep 15 which resetstheSIandbeginstheSI termination process, resultsinthe correctactionbeing atransitiontoE-2whereSI terminationwillbedirected.

c.Incorrect.The Slterminationcriteriais met and atransitionis requiredtobemadetoE-2.Plausible ifthecandidate misappliesthedatagivento required SI termination criteria and determines that continuinginECA-2.1isthe correctactionwhichwouldbe correctisSI terminationcriteriawas not met.D.Incorrect.ThetransitiontoE-2is correct howevertheSI termination is met as providedinthedata suppliedinthequestion.Plausible because the candidate could recognize the pressure increasinginthe#4SG asbeingancriteriaforthetransitiontoE-2 but misapplythedatagiven as not meeting SI termination criteria..Page207 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.82Tier1 Group 1 KIA W/E12G2.1.32 Abilitytoexplainandapplyallsystemlimitsand precautions.

ImportanceRating:3.4 I 3.8 Technical

Reference:

ECA-2.1 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPL271ECA-2.1,B4,&5,&6 Question Source: Bank#-----ModifiedBank

1. X__New-----QuestionHistory:SQNNRCExam 1/2008,SQNBank question ECA-2.1-B.5.A 001 Question Cognitive Level:Memoryor fundamental knowledge_Comprehension or Analysis__X_10CFRPart55 Content: 10CFR55.43.b (5)Comments: 41.10 143.2 145.12Page208 1/2008 SequoyahSRONRCExam 02/08/2008 83.Given the following:Unit1isat 100%RTP.ControlRodDRodsareat220steps.-A singlerodin Control Bank D dropsto115steps.

WhichONE(1)of the following statements describes the BASES for restricting thermal powertolessthanorequalto75

%?AY'EnsuresFuelRod Integrity is maintained during continued operation.

B.Minimize AFD swingsdueto xenon redistribution.

C.Removes requirement to determine QPTR using incore probes.D.Eliminates the requirement to re-evaluate specific accident analysis.A.Correct,Basis states restriction of thermal power provides assurance offuelrod integrity during continued operation.

B.Incorrect,Not part of basis and lowering RX powercancause AFD swings.Plausibledueto AFD being affected during a dropped rod event but powerreductionis nottominimize AFD swings.c.Incorrect,Not part of actions/basis for droppedrod.ThisactionisfromTS3.2.4QPTR.PlausibleduetoQPTRbeing affected by a droppedrod,andthisis a restriction placed on determiningQPTRwith power above 75%powerwithanNIout of service.D.Incorrect, Accident analysis must be performed to ensure analysis remains valid perTechSpecaction.

Plausibledueto Accident analysis being aTSactionwhich must be pertormea.Page209 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.83Tier1Group2 KIA 000003 G2.2.22DroppedControlRod:Knowledgeoflimiting conditions for operations and safety limits.ImportanceRating:3.4I4.1 Technical

Reference:

TS3.1.3.1andBasis Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPL271AOP-C.01B6,B9QuestionSource:

Bank#_ModifiedBank#

---

NewX----QuestionHistory:NewforSQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge__X_Comprehension or Analysis_10CFRPart55 Content:(CFR43.2 I 45.2)10CFR55.43.b (2)Comments:Page210 1/2008 SequoyahSRONRCExam 02/08/200884.Giventhe following:

Unit 1 operating at 86%powerwhenMFP1A trips.-Astherodsare inserting, the OATC observes the following:

Bank D Group 1 remainsat190steps while the Bank D Group2rods are inserting as indicated by RPlsandstep counters.-The OATC placestherod control to MANUAL stoppingrodmotionwith Bank D Group2rodsat148steps.

Which ONE of the following identifies the correct responsetotherod misalignment per AOP-C.01, Rod Control System Malfunction?A.Make repairs then realign the Group1rodstothe Group2rodsper AOP-C.01.B.Make repairs then realign the Group2rodstothe Group1rodsper AOP-C.01.C.Remove the Unit from service within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> in accordancewithTech Specs using GOs.Trip the ReactorandGoto E-O, Reactor Trip or Safety Injection.A.Incorrect,Plausibledueto AOP-C.01 containsstepstorealign a misalignedrodtothe bank but notwiththeconditions statedinthequestion.

B.Incorrect,Plausibledueto AOP-C.01 containsstepstorealign a misalignedrodtothe bank but notwiththeconditions statedinthequestion.

c.Incorrect,withtherods

>12 and<50stepsout ofalignment,Plausibleduetothiscouldbe correct if the rodswerein a bank otherthanO.O.Correct, AOP-C.01directs-Ifmultiplerods misaligned greaterthan12 steps butnomorethan 50stepseachfrom respective banks(withthe misalignedrodsin Control Bank 0)thenTRIPthe reactor and GO TO E-O, ReactorTripor Safety Injection.Page211 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.84Tier1Group2 KIA 000005 AA2.03Abilityto determine and interpretthefollowingastheyapplytothe Inoperable/StuckControlRod:Requiredactionsifmorethanonerodisstuckor inoperable Importance Rating: 3.5/4.4 Technical

Reference:

AOP-C.1,RodcontrolSystemMalfunction Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPL271AOP-C.01 B8 Question Source: Bank#-----ModifiedBank#

---

NewX---QuestionHistory:NewforSQNNRCEXAM1/2008 QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysis

_X__10CFRPart55Content:

43.5/45.13 10CFR55.43.b (5)Comments:Page212 1/2008SequoyahSRONRCExam 02/08/200885.Giventhe following:-Unit1 turbineloadisat40%.

-Condenservacuumisbeinglostduetoair in-leakage.

-OperatorshaveenteredAOP-S.02,Lossof Condenser Vacuum.-Condenser pressureis1.9psiaand increasingat0.1psia/minute.Whichofthe followingarethecorrectactionsin accordance with AOP-S.02forthe current conditions?A.Tripthe turbineandGOTOAOP-S.06, Turbine Trip.B.Tripthe ReactorandGOTO E-O, ReactorTripor Safety Injection.

C.Continue in AOP-S.02, if condenser pressureexceeds'2.7psiaandcanNOTberestoredwithin5min,Tripthe turbineandGOTOAOP-S.06, Turbine Trip.Continue in AOP-S.02 if condenser pressureexceeds2.7psiaandcanNOTberestoredwithin5min,Tripthe ReactorandGOTO E-O, ReactorTriporSafety Injection.A.Incorrect, PlausibleduetoTurbinetripwouldbe required if the loadwerelessthan30%with pressure>1.72 psia.B.Incorrect, Plausibledueto Reactortripwouldbe required if the condenser pressure exceeded2.7 psia and could not be restoredtolessthan2.7psiawithin 5 minutes.The1.72 setpoint is associatedwithturbinetripatlessthan30%load.

C.Incorrect,Plausibleduetowithload greaterthan30%, if the condenser pressure exceeds2.7 psia and cannot be restored within 5minutes,then a Reactortripis required, NOT aTurbinetrip.D.Correct.Withload greaterthan30%,ifthe condenser pressure exceeds2.7 psia and cannot be restored within 5minutes,then a Reactortripisrequired.Page213 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.85Tier1Group2 KIA 051 AA2.02 Ability to determine and interpret the followingasthey applytotheLossof Condenser Vacuum:Conditions requiring reactor andlorturbinetrip Importance Rating: 3.9/4.1 Technical

Reference:

AOP-S.02,Lossof Condenser Vacuum Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

OPL271AOP-S.02B2,B8 Question Source: Bank#-----ModifiedBank

1. __X__New-----QuestionHistory:SQNNRCExam 1/2008,SQNBankMod AOP-S.02-B.2014 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis_X__10CFRPart55 Content: 10CFR55.43.b (5)Comments: 43.5/4.5.13Page214 1/2008 SequoyahSRONRCExam 02/08/200886.Giventhe following:-An inadvertentReactorTripoccurredonUnit1.-A SafetyInjectionwas initiatedduetoSG#2 Atmospheric Relief Valve sticking open.-The operatingcrewis currentlyperformingE-2,FaultedSteam Generator Isolationandthe following conditions exist: RCS subcoolingis64 degrees F.S/G levelsin#1,#3and#4SGsarestableat 33%narrow range.S/G#2levelis 0%widerange.

RCS pressure1760psigandrising.

Pressuizer level 22%andrising.

WhichONE(1)ofthefollowing identifies the proceduralflowpathto implementES-1.1,SI Termination and,therequiredactioninES-1.1ifthe RCS pressurestartstodropand continuestodrop followingtheactiontostopthefirst centrifuqalchargingpump(CCP)?

A.TransitiontoES-1.1wouldbemade DIRECTLYfromE-2.RestarttheCCPand transitiontoE-1,Lossof Reactor or Secondary Coolant.TransitiontoES-1.1wouldbemade DIRECTLYfromE-2.TransitiontoES-1.2,PostLOCACooldown.C.No direct transitionfromE-2toES-1.1canbemade,a transition mustfirstbemadetoE-1,Lossof Reactor or Secondary Coolant.RestarttheCCPand transitiontoE-1,Lossof Reactor or Secondary Coolant.D.No direct transitionfromE-2toES-1.1canbemade,a transition mustfirstbemadetoE-1,Lossof Reactor or Secondary Coolant.TransitiontoES-1.2,PostLOCACooldown.Page215 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,TransitiontoES-1.1wouldbemade directlyfromE-2andifthe RCS pressure continuedtodropfollowingthe stopping oftheCCPthe procedure will directthetransitiontoES-1.2.Plausible because the restarting oftheCCPand atransitiontoE-1wouldbemadefromtheES-1.1FoldOutPageonthe procedure under different conditions.

B.Correct,ES-1.

1wouldbe enteredfromE-2,and iftheRCS pressure continuedtodrop followingthestopping oftheCCP, atransitiontoES-1.2is directed.C.Incorrect,ES-1.1 would be entered directlyfromE-2,NotransitiontoE-1wouldberequired, howeverthecandidate might mistakenlyconcludethatanE-1transitionwouldhavetobemadebeforeES-1.1 couldbeentered.Plausibleifthecandidatewasnotawarethatthe directtransitionwas correct or because the restarting oftheCCPand atransitiontoE-1wouldbemadefromtheES-1.1FoldOutPageonthe procedure under different conditions.D.Incorrect,ES-1.1 would be entered directlyfromE-2,NotransitiontoE-1wouldberequired, however plausible because the candidate might mistakenly concludethatanE-1transitionwouldhavetobemadebeforeES-1.1couldbe entered andthetransitiontoES-1.2is correctforthe pressure response aftertheCCPisstopped.Page216 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.86Tier1Group2 KIA W/E02 EA2.2SITermination:

Adherence to appropriate procedures and operationwithinthelimitationsinthefacility'slicenseand amendments.

ImportanceRating:3.5I4.0 Technical

Reference:

E=O, ReactorTripor Safety Injection Technical Specifications3.3.1.1,3.3.2.1 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPT200.PZRPCS B6, OPT200.NISB6,OPL271 E-O B5 Question Source: Bank#-----ModifiedBank#

---

NewX-----Question History:NewforSQNNRCEXAM 1/2008 QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysisX10CFRPart55Content:

10CFR55.43.b(3,5)Comments: 43.5 I 45.13Page217 1/2008 SequoyahSRONRCExam 02/08/2008 87.Given the following conditions:Unit1core reload in progress.-An irradiated assemblyisinthe manipulator craneandisbeing transportedtoacore location.-An additional irradiated fuel assemblyisinthe RCCA change fixture.The Refueling SRO determines a leak existsinthe Reactor CavitySealand RADCON tech reports that radiation levels are risingasthe waterlevelis dropping.WhichONE(1)of the following describes the action that is REQUIREDtobe takenwiththe2fuel assemblies in accordance with AOP-M.04, Refueling Malfunctions?B.C.D.Irradiated Assembly In Manipulator Crane Transportbackto SpentFuelPitside Transportbackto SpentFuelPitside Place in any core location Place in any core location Irradiated Assembly In RCCA change Fixture Place in any core location Transportbackto SpentFuelPitside Transportbackto SpentFuelPitside Placeinanycore locationPage218 1/2008 SequoyahSRONRCExam 02/08/2008A.Correct.As stated per AOP-M04.B.Incorrect.

AOP-M.04 requires the assemblyintheRCCAfixturetobe placedinthecore.Plausible becausethecandidatecouldthinkthatboth assemblieswouldbe returnedtothe spentfuelpit.C.Incorrect.

AOP-M.04requiresthe assemblyinthe manipulatorcranetobe transportedtotheSFP and the assemblyintheRCCAfixturetobe placedinthecore.Plausible becausethesearetheto locations requiredfortheassemblies, butarereversed.Thecandidate couldthinkthatthe identified locationsarethe requiredlocationforeach oftheassemblies.

D.Incorrect.

AOP-M.04requiresthe assemblyinthe manipulatorcranetobe transportedtotheSFP.Plausible becausethecandidate couldthinkthatthis assembly would be placed in acorelocationPage219 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.87Tier1Group2KIAW/E16G2.2.31High Containment Radiation Knowledge of procedures and Limitations involvedininitialcoreloading.

ImportanceRating:2.2I2.9 Technical

Reference:

AOP-M.04, Refueling Malfunctions Proposed referencestobeprovidedto applicants during examination:

None Learninq Objective:

Question Source: OPL271AOP-M.04, B.8.b Bank#----Modified Bank#X---New-----QuestionHistory:SQNNRC.Exam 1/2008, Modified WBN Bank question AOP2900.06 006 Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis__X_.10CFRPart55 Content: 43.6 10CFR55.43.b (7)Comments:Page220 1/2008 SequoyahSRONRCExam 02/08/2008 88.Given the following:Unit1 restarted 10 days ago following a refueling outageandis operatingat100%power.Control BankDis currently185steps withdrawnandRod controlisin AUTOMATIC.

-Subsequently, the following occurs;-A controller problem resultsinthe Letdown Hx Temperature Control Valve slowly drifting closed.-The operating crew enters AOP-C.02, Uncontrolled RCS Boron Concentration Changes.WhichONE(1)of the following correctly describes the direction the controlrodswouldmove ANDhowrod controlistobe operated in accordance with AOP-C.02?A.OUT Controlrodsaretobe withdrawn in ManualOUT Controlrodsaretobe operated in AutomaticC.IN Controlrodsaretobe inserted in Manual D.IN Controlrodsaretobe operated in AutomaticPage221 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect.Thefirst partwouldbecorrect,Ltdntempwouldincrease resulting in Boration andTavelowerstherforerodswouldmoveoutinAuto.

AOP-C.02 section2.1, Uncontrolled or Unplanned dilution specifically states Control rods are nottobewithdrawnin Manual however Automaticrodmotionisallowed.

B.Correct.Thefirst partwouldbecorrect,Ltdntempwouldincrease resulting in Boration andTavelowerstherforerodswouldmoveoutinAuto.

AOP-C.02 section2.1, Uncontrolled or Unplanned dilution specifically states Control rods are nottobewithdrawninManualhowever Automaticrodmotionisallowed.

C.Incorrect.First and second partincorrect.Ltdntempwouldincrease resulting in Boration andTavelowerstherforerodswouldmoveoutinAuto.

AOP-C.02 section2.1, Uncontrolled or Unplanned dilution specifically states Control rods are nottobewithdrawninManualhowever Automatic rodmotionisallowed.D.Incorrect.First partincorrect.Ltdntempwouldincrease resultinginBorationandTavelowers therforerodswouldmoveoutinAuto.

AOP-C.02section2.1, Uncontrolled or Unplanned dilution specifically states Controlrodsare nottobewithdrawninManualhowever Automaticrodmotionisallowed.Page222 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.88 Tier L Group_1_KIA008 A2.09 ComponentCoolingWater:

Abilityto(a)predict the impactsofthe following malfunctions or operationsontheCCWS,and(b)basedonthose predictions, use procedurestocorrect,control,ormitigatethe consequencesofthose malfunctions or operations:Resultsof excessive exit temperaturefromtheletdowncooler, including the temperature effects on ion-exchange resins.ImportanceRating:2.3/2.8 Technical

Reference:

CCSMechLogicDiagram 1,2-47W611-70-2.

AOP-C.02.Proposed referencestobeprovidedto applicants during examination:

none Learning Objective:

Question Source: OPT200.CVCS B.5.d Bank#-----ModifiedBank#X New-----QuestionHistory:SQNNRCExam 1/2008,Votgle draft2006Exam question#3 Modified Question Cognitive Level: Memory or fundamental knowledge_Comprehension or Analysis_X_10 CFR"Part55 Content: 10CFR55.43.b(6)(5)Comments:(CFR41.5/43.5/45.3/

45.13)Page223 1/2008 SequoyahSRONRCExam 02/08/200889.Ifthe ReactorCoolingSystem pressureexceededthe Technical Specification SafetyLimitinMode3,whichONE(1)ofthe following identifiesthemaximumtimeallowedforeachofthe following?1.PressurerestoredtolessthanSafetyLimit.

2.Operations Duty Manager (ODS)Notification.

A.C.O.Pressure Restored5minutes5minutes 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour ODS Notification Within5minutesafterevent initiation Within5minutesafterREP declaration Within5minutes after event initiation Within5minutes after REP declarationA.Incorrect,Thetimeto restore pressure is 5 minutes per TIS 2.1.2.Thetimeto notifytheODSis 5 minutes aftertheREPdeclaration.Plausible becausethereis a 15minutetime requirementtomake a declaration after eventinitiationandthe student couldmixuptheinitiating requirement.

B.Correct,Thetimeto restore pressure is 5 minutes per TIS2.1.2.ThetimefortheODSnotificationiswithin 5 minutes afterREPdeclaration.

C.Incorrect,Thetimeto restore pressure is 5 minutes per TIS 2.1.2 not 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> statedinthedistractor.Thetimeto notifytheODSis 5 minutes aftertheREPdeclaration.Plausible becausethereis a 15minutetime requirementtomake a declaration after event initiation and the studentcouldmixuptheinitiating requirement.D.Incorrect,Thetimeto restore pressure is 5 minutes per TIS 2.1.2 not 15 as statedinthedistractor.

CorrectODSnotificationtime.Page224 1/2008SequoyahSRONRCExam 02/08/2008 QuestionNo.89Tier2Group1KIA010 PressurizerPressureControlSystemG 2.4.38 Abilitytotakeactionscalledforinthe facility emergencyplan,including (if required)supportingoractingas emergency coordinator Importance Rating: 2.2/4.0 Technical

Reference:

Technical Specifications 2.1.2 Radiological EmergencyPlanEPIP-1 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

Question Source:OPL271REP2, OPT200.PZRPCS B6 Bank#-----ModifiedBank#

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New_X__QuestionHistory:NewforSQNNRCEXAM 1/2008 Question Cognitive Level: Memory or fundamental knowledge_X_Comprehension or Analysis_10CFRPart55 Content: 10CFR55.43.b(1,2)Comments: 43.5/45.11Page225 1/2008SequoyahSRONRCExam 02/08/200890.Giventhe following:Unit1at100

%powerwiththe TP-AFWpumpoutof service for maintenance.

-Annunciator "125VDCVITAL CHARGERIIFAILUREORVITALBATII DISCHARGE"ON1-M-1panelisinalarmandthecrew is investigatingthecause.Followinga reactortripduetoa spurious main turbinetrip,thecrewisperformingES-0.1, ReactorTripResponse,whentheOATC determinestheTrainBAFWpumpisNOTrunning.WhichONE(1)ofthefollowing identifiesareasontheAFWpumpBisnotrunningAND-theallowed procedure use sequenceprovidedbyEPM-4,User'sGuide,to allowplacingtheAFWpumpBin service?A.LossofcontrolpowertoSSPSTrainBslaverelays.AOP-P.02,Loss of125vDCVitalBatteryBoard,canbe implementedONLYafterES-0.1hasbeencompleted.B.Lossofcontrol powertoSSPSTrainBslaverelays.

Implement AOP-P.02,Lossof125vDCVitalBatteryBoardwhile continuinginES-0.1.C.Lossofcontrolpowertothe 6900v Shutdown Board.AOP-P.02,Lossof 125vDCVital BatteryBoard,canbe implementedONLYafterES-0.1hasbeen completed.Lossofcontrolpowertothe 6900v Shutdown Board.Implement AOP-P.02,Lossof125vDCVital Battery Board while continuinginES-0.1.Page226 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect,Loss of Control Powerfortheslave relay would prevent the pumpfromstarting.

Control powertoSSPSTrain B slave relaysisfrom Channel II 120v ACVitaland notfromthe ChannelII125vDC.Candidatecouldconfusethe 2 powersupplies.Rules of procedure usage allows implementing AOP while continuing ES-O.1.Plausible if studentthinksthe AOP cannot be performed while ES-O.1isbeing performed.

B.Incorrect,Loss of Control Powerfortheslave relay would prevent the pump-fromstarting.

Control powertoSSPSTrain Bslaverelaysisfrom Channel II120vACVitaland notfromthe ChannelII125vDC.Candidatecouldconfusethe 2 powersupplies.While125vDC control Powertothe boardcanbe transferred, the control powertotheslave relays cannot be transferred.

Rules of procedure usage allows implementing AOP while continuing ES-O.1.C.Incorrect,Loss of control powertothe 6900v Shutdown Boardwouldbringinthealarm and without the control power the pumps would notstart.Rules of procedureusageallows implementing AOP while continuing ES-O.1.Plausible if studentthinksthe AOP cannot be performed while ES-O.1 is being performed.D.Correct,Loss of control powertothe 6900v Shutdown Boardwouldbringinthealarm and without the control power the pumps would notstart.Rules of procedure usage allows implementing AOP while continuing ES-O.1.Page227 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.90 Tier 2 Group 1K/A013 A2.05 Abilityto(a)predict the impactsofthe following malfunctions or operationsonthe ESFAS;and(b)basedon those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations;Lossofdc control power ImportanceRating:3.7/4.2 Technical

Reference:

AOP-P.02, and 0-SO-250-10, 6900V ShutdownBoardDC Control Bus Transfer,1-AR-M1-C (B-4)Proposed referencestobe provided to applicants during examination:

None Learning Objective:

OPL271AOP-P.02 B2&8 Ouestion Source: Bank#-----Modified Bank#-----New X---Question History: NewforSQNNRCEXAM 1/2008 Question Cognitive Level: , Memory or fundamental knowledge_Comprehension or Analysis_X__10CFRPart55 Content: 10CFR55.43.b (5)Comments: 41.5/43.5/45.3/45.13Page228 1/2008 SequoyahSRONRCExam 02/08/2008 91.Given the following:

Unit1is being shutdown for a refueling outage.Operating crew is performing 0-GO-7, Unit Shutdown From Hot Standby To Cold Shutdown.WhichONE(1)of the following identifies when Containment Closure Control is requiredtobe implemented in accordance with 0-GO-15, Containment Closure Control, ANDwhowill maintain the listing of Containment Closure Exceptions in effect in accordance with 0-GO-15?A':I B.C.D.Required When When Unit entersMode5 When Unit enters Mode 5 When RHR is placed in service When RHR is placed in service Containment Closure Exceptions Maintained by Operations Work Control Center(WCC)

US Unit 1 SRO Operations Work Control Center(WCC)

US Unit 1 SROPage229 1/2008 SequoyahSRONRCExam 02/08/2008A.Correct, 0-GO-7statesthat 0-GO-15 , ContainmentClosureControl,isto be implementedtotrack containment configuration changeswhentheunit enters Mode 5.0-GO-7identifiestheWCCUS as maintaining the Appendix tracking containmentclosureexceptions.B.Incorrect, 0-GO-7statesthat 0-GO-15 , ContainmentClosureControl,isto be implementedtotrack containment configuration changeswhentheunitentersMode 5.0-GO-7identifiestheWCCUS as maintaining the Appendix tracking containmentclosureexceptions.Plausible because the GO requirestheunitSROtomaintain awareness of the exceptionsandtoinformtheWCCUS of changesontheunitthat could affect allowableclosuretimes.

C.Incorrect, 0-GO-15 purpose statementsaysthe GO provides the requirements for Containment Closure Controlinthe event of a loss of RHR shutdown cooling, making the implementation fo the GOwhenRHR is placedinserviceplausible,however,the correct implementationiswhentheUnit entersMode5.D.Incorrect, 0-GO-15 purpose statementsaysthe GO provides the requirements for Containment Closure Controlinthe event of a loss of RHR shutdown cooling, making the implementation fo the GOwhenRHR is placedinserviceplausible,however,the correct implementationiswhentheUnit enters Mode 5.Plausible because the GO requirestheunitSROtomaintain awareness of the exceptions andtoinformtheWCCUS of changesontheunitthatcould affect allowableclosuretimes.Page230 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.91Tier2Group1K/A103 Containment Systems G 2.2.14 Knowledgeofthe processformaking configuration changes.ImportanceRating:2.1/3.0 Technical

Reference:

0-GO-15, Containment Closure Control Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:OPL271GO-15B.1andB.4 Question Source: Bank#-----ModifiedBank#

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NewX----QuestionHistory:NewforSQNNRCEXAM1/2008 Question Cognitive Level: Memory or fundamental knowledge__X_Comprehension or Analysis_10CFRPart55 Content: 10CFR55.43.b(4,5)Comments: 43.3/45.13Page231 1/2008SequoyahSRONRCExam 02/08/200892.Giventhe following:Unit1isinMODE4withHeatupinProgress.Unit2isinMODE6withcorereloadinprogress.

WhichONE(1)ofthefollowing identifies a conditionwherethe associated Unit's ContainmentPurgewouldberequiredtobeshutdown, but would continuetorununtilan Operator MANUALLYshutdownthepurge?

A.Annunciator, 1-RA-90-131ACNMTPURGEAIREXHMONHIGHRAD,alarmswithUnit1Upper ContainmentPurgeinprogress.

B.Annunciator, 0-RA-90-101AAUXBLDGVENT MONITORHIGHRAD,alarmswithUnit1Lower ContainmentPurgeinprogress.

C.Annunciator, 2-RA-90-131ACNMTPURGEAIREXHMONHIGHRAD,alarmswithUnit2Lower ContainmentPurgeinprogress.Annunciator, 0-RA-90-101AAUXBLDGVENT MONITORHIGHRAD,alarmswithUnit2Upper ContainmentPurgeinprogress.A.Incorrect,Plausibleif studentdoesnot rememberthat1-RM-90-131would automaticallyshutdowntheU-1 purge and manualshutdownisnotrequired.

B.Incorrect,Plausibledueto 0-RM-90-101willinitiateanABI,however, Manual shutdown ofpurgeis NOT requiredduetothe ABI ifU-1isinMode4.

c.Incorrect,Plausibleif student does not rememberthat2-RM-90-131would automaticallyshutdowntheU-2 purge and manualshutdownisnotrequired.D.Correct,O-RM-90-101willinitiatean ABI and iftheUnitisin MODE5,6,ordefueled, an operator must manuallyshutdowntheU-2purge.Page232 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.92Tier2 Category 2KIA029G2.4.46Abilityto verifythatthealarmsare consistentwiththeplantconditions.ImportanceRating:3.5/3.6 Technical

Reference:

0-SO-30-3, 1 ,2-47W611-30-6, 0-AR-M12-B(B-1andB-2)

Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:QuestionSource:New OPT200.CONTPURGE B5QuestionHistory:NewforSQNNRCEXAM1/2008QuestionCognitiveLevel:

Higher10CFRPart55 Content:43.5/45.3/45.12 10CFR55.43.b(7)(4)Comments:Page233 1/2008SequoyahSRONRCExam 02/08/200893.YouaretheFuelHandlingSROforreceivingnewfuel.Asanewfuelcaskisbeingliftedfromthe transporttruck,theliftingslingsbreakandthecaskdropstotheground.

Initial inspections indicateextensivedamagetoonefuelassembly.PerAOP-M.04,RefuelingMalfunctions,whichONE(1)ofthe following correctly describestheMINIMUMlevelrequiredforapprovalofrecovery instructions?A.FuelHandlingSRO.B.ShiftManager.

C.Operations Manager.PlantManager.A.Incorrect,Plausibleif student does not know rec<?very instructions arerequired.Fuel Handling SRO approvalforfuel movement is normally required.B.Incorrect,Plausible because Fuel Handling SRO approvalforfuel movement is normally requiredandsincedamage occured Shift Manager approvalwouldbe a good distractor.

c.Incorrect,Plausible if student knows recovery instructions are required prior to moving damagedfuelassembly, and since operationsisincharge of the movement the Operations Manager is a good distractor.D.Correct,Mustbesuspendeduntilrecovery instructionsareapprovedbythePlantManager.

""Page234 1/2008SequoyahSRONRCExam 02/08/2008QuestionNo.93 Tier L Group LK/A034A2.02 Fuel Handling Equipment:Abilityto(a)predicttheimpactsofthefollowing malfunctions or operationsontheFuelHandlingSystem;and(b)basedon those predictions, use procedurestocorrect,control,ormitigatethe consequencesofthose malfunctions or operations:Droppedcask.ImportanceRating:3.4/3.9 Technical

Reference:

AOP-M.04 Refuleing Malfunctions Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:QuestionSource:

OPL271AOP-M.04B5and8 Bank#-----ModifiedBank#

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NewXQuestionHistory:NewforSQNNRCEXAM1/2008 Question Cognitive Level: Memory or fundamentalknowledgeX ComprehensionorAnalysis_10CFRPart55 Content: 10CFR55.43.b (7)Comments:(CFR41.5/43.5/45.3/

45.13)Page235 1/2008 SequoyahSRONRCExam 02/08/200894.Giventhe following:BothunitsinMODE1.-The followingdataresultedfromthe weekly testing on 125v DC Vital Battery III.Battery on float charge.Battery Terminal Voltage 133v dc.Battery charging currentis2.2amps.

BatteryRoomand Electrolyte temperatureis68°F.-Cell electrolytelevelisbetweenminimumandmaximummarks.-Cell voltageis2.11vdc.

-Corrected Specific Gravityis1.197.WhichONE(1)ofthe following identifiestheUnit1T/S required actions regarding the 125vDCVital Battery III?REFERENCE PROVIDED A.Immediately declare INOPERABLEdueto Category A criteria,restoreto OPERABLE statuswithinthenext2hoursorbeinat least HOT STANDBYwithinthenext6 hoursandinCOLD SHUTDOWNwithinthe following30hours.B.Immediately declare INOPERABLEdueto Category B criteria,restoreto OPERABLE statuswithinthenext2hoursorbeinat least HOT STANDBY withinthenext6hoursandinCOLD SHUTDOWNwithinthe following30hours.Maybe considered OPERABLE provided that within24hoursallthe Category B measurementsaretakenandfoundtobe within their allowablevalues,and provided all parameter(s)arerestoredtowithin limits withinthenext6days.D.Maybe considered OPERABLE provided all Category B measurements are within their allowable values and provided the parameter(s) arerestoredto within limits withinthenext7days.No requirementexiststo verify Category B measurements within allowable values within24hours.Page236 1/2008SequoyahSRONRCExam 02/08/2008 A.Incorrect,Theconditions stateddonotrequire declaring INOPERABLE eventhoughthecell FloatVoltagelimitandSpecific Gravitylimitare NOT met duetothe weeklytestaretoverifythatthe pilot cell parameters meet Category A limits and if theydonot,thenfootnote (1)provides for considering the battery operable provided Category B measurementsaretakenwithin24 hours and foundtobewithintheir allowablevalues.Plausible becauseifthe footnote (1)isnotusedcorrectly,thecandidatecouldchoosethisresponse.

The actions statedarethe actionsfornot meetingtheLCO.B.Incorrect,Theconditions stateddonotrequire declaring INOPERABLE eventhoughthe FloatVoltageis below the Category Blimit,therehasbeenno correction for temperature as identifiedby(c)andthevoltageisabovethe Category B allowable value.Theweeklytestaretoverifythatthe pilot cell parameters meet Category A limits and do not measuretoverifyall Category Bcriteria.Plausible becauseifthe footnotes(1),(2), and(c)are not used correctly, the candidatecouldchoosethisresponse.The actions statedaretheactionsfor not meetingtheLCO.C.Correct,The weekly test measuretoverifythe pilot cell meets the Category A limits and if asinthiscasetheFloatvoltage andtheSpecific Gravity limit are notmet,thenfootnote (1)containsthe required actionswhichare as statedintheanswer.D.Incorrect,Thischoicewhichisfootnote (2)would result in afailureto meetthe24 hour requirement to perform the Category B measurements and also could extendthetimeto restore the parameterstowithin allowablevalues.Plausibleifthe candidate applies footnote (2)duetothe Float Voltage being below the Category Blimitlisted.Page237 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.94Tier3 KIA G2.1.12Abilityto apply technical specifications forasystemImportanceRating:2.9 I 4.0 Technical

Reference:

TIS,ElectricalPowerSystemsD.C.Distribution-Operating,LCO3.8.2.3 Proposed referencestobeprovidedto applicants during examination:T/S 3.8.2.3 (4 pages)LearningObjective:

OPT200.DC B6QuestionSource:

Bank#----ModifiedBank#

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NewXQuestionHistory:NewforSQNNRCEXAM 1/2008QuestionCognitiveLevel:Memoryor fundamental knowledge_ComprehensionorAnalysis

_X_10CFRPart55 Content: 10CFR55.43.b (2)Comments:43.2/43.5/45.3Page238 1/2008SequoyahSRONRCExam 02/08/200895.Giventhe following:-Unit2isinMode5.-At0130theControlRoomEmergency Ventilationsystem(CREVS)TrainBwas started.-At0200theCREVSTrainAwasremovedfromservicefor heaterrepair,withrepairsexpectedtobecompleted.in12hours.-At0530theCREVSTrainB breakertrippedonoverload.WhichONE(1)of the.following describesUnit2TechSpec3.7.7"ControlRoom Emergency Ventilation System" applicabilityforthisconditionANDthebasisforthisTechSpec?A.TechSpec3.7.7wouldNOTbeenteredinthismode.Limitsthe radiationexposuretopersonnelinthecontrolroomto5remorlesswholebody following all credible accident conditions.B.TechSpec3.7.7wouldNOTbeenteredinthismode.Limitstheradiationexposuretopersonnelinthecontrolroomto1remorlesswholebodyfollowingall credible accident conditions.TechSpec3.7.7wouldbeenteredinthismode.Limitstheradiationexposuretopersonnelinthecontrolroomto5remorlesswholebody following all credible accident conditions.D.TechSpec3.7.7wouldbeenteredinthismode.Limitstheradiationexposureto personnelinthecontrolroomto1remorlesswholebodyfollowingall credible accident conditions.Page239 1/2008 SequoyahSRONRCExam 02/08/2008A.Incorrect, Plausible if student believesTechSpec 3.7.7 is not applicable ingivenmode.

Limiting control room personnel to 5remorlesswhole bodyfollowingallcredible accidentconditionsis correct perthebasis.B.Incorrect, Plausible if student believesTechSpec 3.7.7 is not applicable ingivenmode.

Limiting control room personnel to 1remisincorrect.

C.Correct,TechSpec 3.7.7wouldbe applicableingivenMode, and per thebasisforthisTechSpecLimits"the radiation exposure to personnelinthe controlroomto 5remorlesswhole bodyfollowingallcredible accident conditions.D.Incorrect,TechSpec 3.7.7wouldbe applicableingivenMode.Limiting control room personnel to 1remis incorrect perthebasisPage240 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.95 Tier--LK/AG 2.1.33 Ability to recognize indicationsforsystem operating parameterswhichare entry-level conditions for technical specifications.

Importance Rating: 3.4/4.0 Technical

Reference:

TechSpec3.7.7andbasis,TechSpec3.0.4 Proposed referencestobe provided to applicants during examination:

None Learning Objective:

OPT200.CBVENTB2,5,6 Question Source: Bank#-----ModifiedBank#

_NewX--QuestionHistory:NewforSQNNRCExam1/2008 Question Cognitive Level: Memory or fundamental knowledge_ComprehensionorAnalysisX10CFRPart55 Content: 10CFR55.43.b (2)Comments:(CFR43.2/43.3/45.3)Page241 1/2008 Sequoyah SRONRCExam 02/08/200896.An engineer has submitted a design change request to replace the controller for FCV-62-93,"Charging Flow Control,"witha different type of controller to improve pressurizer level control at low power.Which ONE (1)of the following correctly describes the MINIMUM required qualifications for the person(s)PREPARING the safety evaluation paperwork in accordancewithSPP-9.4, 10CFR50.59 Evaluations of Changes, Tests, and Experiments?50.59 qualified ONLY.B.SRO Licensed Operator ONLY.C.Degreed Engineer AND 50.59 qualified.

D.SRO Licensed Operator AND 50.59 qualified.A.Correct.

10CFR50.59 qualified individuals shall (1)be technically qualified managers, supervisors, engineeringspecialists,TVA personnelwhoare degreed engineers with a minimum of four years nuclear experience or equivalent per BP-105, licensed (or formerly licensed)operators or equivalent contract personnel, or recognized subject matter experts approved bythesite 10CFR50.59 Program Manager and (2)have completed the required 10CFR50.59 training.B.Incorrect.Not requiredtobe licensed and requiredtobe50.59qualified.Plausible if student thinks havinganSROLicenseisthe minimum requiredduetowhatittakestoget a license.c.Incorrect.Not requiredtobe a licensedengineer.Plausibleif studentthinkshaving a Degree and knowing individual mustbe50.59qualified.

Student may think a degreed Engineer may be requireddueto Engineering being involved with plant.design.D.Incorrect.Not requiredtobe a licensedSRO.Plausibleif studentknowsthe individual mustbe50.59 qualified and may think havinganSROLicenseisalso requireddueto what ittakestoget a license.Page242 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.96 Tier--LK/A2.2.8 Knowledgeoftheprocessfor determiningifthe proposedchanqe,test,or experiment involves an unreviewed safety question.Importance Rating: 1.8/3.3 Technical

Reference:

SPP-9.4 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:

Question Source:NoLesson Objective identified Bank#XModifiedBank

1. -----New-----QuestionHistory:SQNBank SPP-9.49,SQNNRCEXAM1/2008 Question Cognitive Level: Memory or fundamental knowledge X Comprehension or Analysis_10CFRPart55 Content: 10CFR55.43.b (3)Comments:(CFR43.3/45.13)Page243 1/2008SequoyahSRONRCExam 02/08/200897.Giventhe following:-Unit2isinMode4-The Chemistry Lab Technician notifiesthecontrolroomthatboththeInsideand Outside ContainmentRCSHotlegSample isolationvalvesfailedtocloseafter drawingasample.Whichofthe followingiscorrect concerningtheinitialactiontime requirement the applicabilityofthe associated31day penetration isolation verification requirementduetothe failurelistedabove (incorporating ALARA considerations),iftheselected isolationvalveisinaHigh Radiation Area?Action A':IIsolatewithin1 hourB.Isolatewithin4hoursC.Isolatewithin1hourD.Isolatewithin4hours31day Penetration Isolation VerificationIsrequired every surveillance periodandcanbeverifiedClosedby administrative meansIsrequired every surveillance periodandcanbeverifiedClosedby administrative meansIsNOTrequirediftheselected penetration isolationvalveislockedintheClosed positionIsNOTrequirediftheselected penetration isolationvalveislockedintheClosed positionPage244 1/2008SequoyahSRONRCExam 02/08/2008A.Correct.

Per TS 3.6.3theactionistoisolatethe penetration within 1hour.The31 day surveillance would always be applicable but pernoteat bottom ofTScanbeverifiedusing administrative means.B.Incorrect.

Per TS 3.6.3the'actionistoisolatethe penetration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.So the 4 houractioniswrong.The 31 day surveillance would always be applicable but pernoteat bottom ofTScanbeverifiedusing administrative means.c.Incorrect.

Per TS 3.6.3theactionistoisolatethe penetration within 1hour.The31 day surveillance would always be applicable but pernoteat bottom ofTScanbeverifiedusing administrativemeans.Plausible if studentthinksthatduetoALARA concerns the 31 day verification requirementcanbe waived ifthevalveis locked closed.D.Incorrect.PerTS 3.6.3theactionistoisolatethe penetration within 1hour.The31 day surveillance would always be applicable but pernoteat bottom ofTScanbeverifiedusing administrativemeans.Plausible if studentthinksthatduetoALARA concerns the 31 day verification requirementcanbewaived ifthevalveis locked closed.Page245 1/2008 SequoyahSRONRCExam 02/08/2008 QuestionNo.97 Tier--LK/A2.3.1 Knowledgeof10CFR:20andrelatedfacilityradiationcontrol requirements.

ImportanceRating:2.6/3.0 Technical

Reference:

TechSpec3.6.3 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:NoneIdentified Question Source: Bank#---ModifiedBank

1. ----New__X__QuestionHistory:SQNNRCEXAM1/2008 QuestionCognitiveLevel:Memoryor fundamental knowledge X ComprehensionorAnalysis_10CFRPart55Content:(CFR41.12/43.4/45.9/

45.10)10CFR55.43.b (2)Comments:Page246 1/2008SequoyahSRONRCExam 02/08/200898.Giventhe following conditionsonUnit1:-YouaretheUnitSupervisor.

Rad Waste water inventory is approaching storage capacity.-Areleaseofthe MonitorTankisplanned.-Sample resultsindicatenon gaseous activityinthetankis slightly higherthanthe3.0E-5uci/mlvaluelistedinO-SI-CEM-077-400.1,Liquid Waste EffluentBatchRelease,for openingaBatchReleasePermit.-The sourcecheckon 0-RM-90-122,LiquidRadwasteRelease Monitorhasfailed.-TheShift Manager has declared 0-RM-90-122,LiquidRadwaste Release Monitor Inoperable.WhichONE(1)ofthefollowing statements is correct regarding approving/disapprovingthepermitfor releasing the MonitorTankin accordance with O-SI-CEM-077-400.1?A.Approvalnotpermitted.Cannotrelease Monitor Tankuntilcontentsisreprocessedtolower activity.B.Approvalnot permitted.Cannotrelease monitortankuntilO-RM-90-122hasbeenreturnedto OPERABLE status.Approvalispermitted.Provideditisreleasedin accordancewithODCM.Shift Manager approvalisrequiredforreleasedueto activity level.D.Approvalis permitted.Provideditisreleasedin accordancewithODCM.Shift Manager approvalisNOTrequiredfor releaseatthis activity level.Page247 1/2008SequoyahSRONRCExam 02/08/2008A.Incorrect, RMdoesnot requiredtobeoperable as long as 2 Independent samples of tank contentsareanalyzed, 2 Independent discharge valve.alignment, 2 Independentreleaserate calculations are verified per aDCM 1.1.1.High activity level requires SM approvalforrelease.Plausibleif studentknowshigh activity limit but does notknowthatthe SM canauthorizetherelease.

B.Incorrect, 2 Independent samples of tank contentsareanalyzed,2 Independentdischargevalvealignment, 2 Independent release rate calculationsareverified per aDCM1.1.1.High activity level requires SM approvalforrelease.Plausible if student believesthatto release atankwith high activityitwouldrequireactive monitoringduringtherelease.

c.Correct, 2 Independent samples of tank contentsareanalyzed,2 Independentdischargevalvealignment, 2 Independent release rate calculationsareverified per aDCM 1.1.1.The high activity level requires SM approvalforrelease.

D.Incorrect, 2 Independent samples of tank contentsareanalyzed,2 Independent dischargevalvealignment, 2 Independent release rate calculationsareverified per aDCM1.1.1.The high activity level requires SM approvalforrelease.Plausibleis student does not know requirement to have SM approval for releasingtankwithhigh activitylevels.Raisingdilutionflowaddstothe plausibility ofbeingabletoreleasewith a higher activity versus getting additional approvals.Page248 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.98 Tier---L KIA 2.3.6 Knowledgeofthe requirementsforreviewingand approvingreleasepermits.

ImportanceRating:2.1I3.1 Technical

Reference:

0-SI-CEM-077-400.1Liquid Waste EffluentBatchRelease.ODCM1.1.1andTable1.1.1.

0-SO-77-1, WasteDispoalSystem,Rev46 Proposed referencestobeprovidedto applicants during examination:

None Learning Objective:QuestionSource:

OPT200.LRW BO, B6 Bank#-----ModifiedBank

1. X----New-----QuestionHistory:DraftVogtle2006ExamSQNNRCEXAM 1/2008 Question Cognitive Level:Memoryor fundamental knowledge X Comprehension or Analysis_10CFRPart55Content:

10CFR55.43.b (2)Comments:(CFR43.4 I 45.10)Page249 1/2008SequoyahSRONRCExam 02/08/200899.Giventhe following:-Mode5.-RCSBoron Concentration=2210ppm.-Required ShutdownMarginBoron Concentration=2100ppm.-RWST Boron Concentration=2600ppm.-ChemistryreportsVolumeControlTankBoron Concentration=2000ppmdueto Primary Water inleakageintotheVCTwhichhasnowbeenstopped.-RCSisbeing drainedto696'formaintenance,per 0-GO-13,"Reactor CoolantSystemDrainandFill Operations."-RCSlevelis inadvertentlyloweredto695'.-RHRpumpamps, dischargepressure,and flowbeginto fluctuate excessively.

WhichONE(1)ofthe following describestherequired action(s)and mitigatingresponsein accordancewithAOP-R.03,RHRSystem Malfunction, and Technical Specifications?

Action A':"StopRHRPumpB.StopRHRPumpC.LowerRHRPumpFlowrateto1000-1500gpmD.LowerRHRPumpFlowrateto1000-1500gpm Mitigating ResponseRaiseRCSlevelusing RWST gravity fill.RaiseRCSlevelusingchargingpumptaking suctionfromVCTRaiseRCSlevelusing RWST gravity fillRaiseRCSlevelusingchargingpumptaking suctionfromVCTPage250 1/2008 SequoyahSRONRCExam 02/08/2008 A.Correct-The required proceduralactiontotriptheRHR pumpiscorrect.The mitigating'actionis correctduetoTechSpec 3.4.1.4 action requirement to not diluteRCSwith concentrationlessthan required by shutdownmargin.The RWST Concentration is greater than requiredSDMconcentration.

B.Incorrect-The required proceduralactiontotriptheRHR pumpiscorrect.The mitigatingactionis incorrectduetoTechSpec 3.4.1.4 action requirementtonotdiluteRCSwith concentrationlessthan required by shutdownmargin.TheVCT Concentrationislessthan required SDM concentration.Plausibleis student does not rememberthisrequirement.

C.Incorrect-The required proceduralactionistotriptheRHRpump.

Lowering theflowrateis plausibledueto procedure containingactionsto lowerflowratetothevalueslistedifRCSlevelis greater than 695'4".SinceRCS levelislessthanthat as statedinthestemthenthisactionwould not be performed andisincorrect.The mitigatingactionis correctduetoTechSpec 3.4.1.4 action requirement to not diluteRCSwith concentrationlessthan required by shutdownmargin.The RWST Concentration is greater than required SDM concentration.

D.Incorrect-The required proceduralactionistotriptheRHRpump.

Loweringtheflowrateis plausibledueto procedure containingactionsto lowerflowratetothevalues.

listed if RCS level is greater than 695'4".SinceRCS levelislessthanthat as statedinthestemthenthisactionwould not be performedandisincorrect.Themitigatingactionis incorrectduetoTechSpec 3.4.1.4 action requirement to notdiluteRCSwith concentrationlessthan required by shutdownmargin.TheVCT Concentrationisless than required SDM concentration.Page251 1/2008"SequoyahSRONRCExam 02/08/2008QuestionNo.99Tier3KIAG2.4.9 Knowledgeoflowpower I shutdown implications in accident (e.g.LOCAorlossofRHR)mitigationstrategies.ImportanceRating:3.3I3.9 Technical

Reference:

AOP-R.03,TechSpec3.4.1.4 Proposed referencestobeprovidedto applicants during examination:

NoneLearningObjective:

OPL271AOP-R.03 83,9QuestionSource:Bank#X--ModifiedBank#

_New-----QuestionHistory:SQNNRCExam 1/2008,SQNBank AOP-R.03-B.0 001 Question Cognitive Level:Memoryor fundamental knowledge_ComprehensionorAnalysis

_X_10CFRPart55 Content: 10CFR55.43.b(2,5)41.10/43.5/45.13Comments:ModifiedBankquestionCandD distractors to eliminate subsetissuesandfor plausibility Page 252 1/2008 SequoyahSRONRCExam 02/08/2008100.Giventhe following:-An event is occurringonUnit1 that requires an ALERT emergency be declared in accordancewiththe Radiological EmergencyPlan(REP).-The ShiftSTA doesNOThaveanactiveSRO license.Priortomakingthe declaration the Shift Manager becomes incapacitatedduetoa medical problem.WhichONE(1)ofthe following identifiesboththe individualwhois responsibileforthemakingtheREP declaration in accordancewithEPIP-1, Emergency Plan ClassificationMatrix,andthe requirement for conducting Assembly and Accountibility in accordancewithEPIP-3, Alert?A.C.D.Responsible for making REP Declaration Unit Supervisor Unit Supervisor Shift Technical Advisor Shift Technical Advisor Assembly and Accountibility Required NOT requiredbutcanbe conducted.

Required NOT requiredbutcanbe conducted.Page253 1/2008 SequoyahSRONRCExam 02/08/2008 A.Incorrect,First part correctPerEPIP-1 Purpose" The responsibility for declaringanemergency, basedonthecriteriainthis procedure, belongs to the SMorSED,the designated Unit SupervisorwhenactingastheSM,ortheTSCSED.

Second part incorrect.

A Site Area Emergencyisthe lowest level REP declaration where performance ofEPIP-BisREQUIRED.PlausibleduetoEPIP-Bisnot requiredinallREPdeclarations.

B.Correct, Per EPIP-1 Purpose" The responsibility for declaring an emergency, basedonthecriteriainthis procedure, belongstothe SM orSED,the designated Unit Supervisor when actingastheSM,ortheTSCSED.PerEPIP-3, Alert EPIP-B Personnel accountablilityandEvacuationcanbe performed but is not required.ASiteArea Emergencyisthe lowest level REP declaration where performance ofEPIP-8isREQUIRED.

C.Incorrect,Plausibledueto ST A does backuptheSEDonREP declarations but by procedure does nothavethe responsiblility for making the declarations.

ASiteArea Emergencyisthe lowestlevelREP declaration where performance ofEPIP-BisREQUIRED.

PteusibieduetoEPIP-Bis not requiredinallREPdeclarations.D.Incorrect, PlausibleduetoSTAdoes backuptheSEDonREP declarations but by procedure does nothavethe responsiblility for making the declarations.

Second partcorrect.PerEPIP-3, Alert EPIP-8 Personnel accountablility andEvacuationcanbe performed but is not required.A Site Area Emergencyisthe lowest level REP declaration where performance ofEPIP-8isREQUIRED.Page254 1/2008 SequoyahSRONRCExam 02/08/2008QuestionNo.100 TierK/AG2.4.40 Emergency Procedures/Plan:KnowledgeoftheSRO's responsibilities in emergency plan implementation.ImportanceRating:2.3/4.0 Technical

Reference:

EPIP-1purpose,EPIP-3,EPIP-8 Proposed referencestobeprovidedtoapplicantsduring examination:

NoneLearningObjective:QuestionSource:OPL271REP Bank#----ModifiedBank#X

--New_QuestionHistory:SQNNRCEXAM1/2008:

SQN question REP-B.1.C 006 modified by adding the first part of the question.QuestionCognitiveLevel:Memoryor fundamental knowledge__X__ComprehensionorAnalysis_10CFRPart55 Content: 10CFR55.43.b (5)Comments: (CFR45.11)Page255