ML081900145
| ML081900145 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 06/03/2008 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML081900145 (110) | |
See also: IR 05000390/2008301
Text
FinalSubmittal(BluePaper)
'vviA IT_;, r3'Ac.(F k/h 1<!\.\f j t FINAL RO WRITTEN EXAMINATION
AND REFERENCES
Watts Bar Nuclear Plant NRC Initial License Written Examination-2008 Master Examination
Please note: The following 100 pages are the Master Examination
copy.Questions 1 through 75 were administered
to the RO candidates
and to the SRO candidates.
Questions 76 through 100 were administered
only to the SRO candidates.
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR QuestionNumber:1Giventhe following plant conditions:*A reactortriphas occurred.*Off-Site powerislost.*All other equipment has functioned
as designed.*The crew is entering ES-O.1, REACTOR TRIP RESPONSE.Upon entenngES-O.1,Step3
directs the operators to monitorforRCS temperature
trending to 55TF.Which temperature
indicationwillthe operatorsuseand why?A.Tavg,to ensure adequateRCSheat removal is occurring.B.Tavg,to check for natural circulation
established.
CTcold,to ensure adequateRCSheat removal is occurring.D.Tcold,to
check for natural circulation
established.
1 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 2 Given the following plant conditions:*A200gpmRCSleakisin
progress.*Containment
pressure is stable at 3 psig.For these plant conditions, whatisthe MINIMUM S/G water level requiredinat leastoneS/Gandwhy?A.29%.Ensures adequate feedwaterfloworS/G inventory to ensure a secondaryheatsink.B.39%.Ensures S/G tubes are covered in order to promote reflux cooling.C.29%.Ensures S/G tubes are covered in order to promote reflux cooling.D.39%.Ensures adequate feedwaterfloworS/G inventory to ensure a secondaryheatsink.2 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 3Giventhe following:*Unit1at22%
reactor power.*RCP#1tripsduetoa
bearing failure.WhichONEofthe following identifies
the immediate effect thattheRCPtripwillhaveonLoop1
\TANDonSG#1 level?Loop1 L'.T A.Decreases B.Increases C.Decreases D.IncreasesSG#1Level Increases Increases Decreases Decreases3of100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 4Giventhe following plant conditions
- TheUnit isat45%.*Letdown i s in service at120gpmp er Chemistry request.Th e OAC observes the following ind ication s on 1-M-6:*VCT level i s 38%and decreasing.
- Annunciato
r W indow 109-A, VCT LEVEL HIILO,isLIT.*1-LCV-62-118
indicatinglightisLITforD
ivert to Holdup Tank.A ssuming NO operator actions ,andbasedon
these indications, actual VCTlevelwill lower t o...A.a level which will cause eventuallossofCCP suction.B.a l evel whichwillc ause a swapovertotheRWST.
C.2 0%and causeauto makeupflowtomaintain 20%level.D.20%and cause auto makeupflowtoreturnlevelto41
%.4 of 100
WattsBar Nuclear Plant2008Initial
License Wr itten Exam SENIOR REACTOR OPERATOR Question Number: 5 Given the follow ingplant condi tions:
- Unit isin RHR coolingwithTr
ainAin servic e i n normal alignment.
- RC S condi tions initiallyare
- Temper aturea t 220°F.*Pressurea t330psig.*Pressuri zer levela t 3 0%.*A transien t occur s causingtheRCSpr e ssur e tostart risingandt he c r ew entersAOI-14, LossofShutdown Cooling.The cre w a lso notes the following annunc iator is LIT:*Annunciator
113E, R HR SUCTFCV-74-1 , 2 , 8 ,9OPEN&HI PRE SS.In response t o increasing
RCSp ressu re , which ON E o f thefollowing identifies
- (1)W hy the Hotleg Loop4 RHR suctio n valves, 1-FCV-74-1and1-FCV-74-2, are direct e dtobe closed?AND (2)A.(1)(2)B.(1)(2)C.(1)(2)D.(1)(2)Whata re t he i mp licatio ns o f Annunciator 1 1 3EbeingLI T?To prote cttheR HR lo w p ressure suction piping.Atleasto ne of the valvesfailedtoclose automaticallywh
en pres sure reac hed setpoint.T o prote ctthe R HR lowpressure suction piping.With th e valves closed, at leastoneofthe valves could NOTbereopened.Toensure availab le ECCS makeupc apacityi s not exceededifsuctionrelief valve op ens.A t leastoneo f the valves failedtoc lose automatically when pressurereached setpoint.T o ensure available ECC S makeup capaci tyisno t e xceededifsu ction relief valve o pens.W i ththeva l ves c losed, a t least o ne of thevalves c ould NOT b e reopened.5 o f 10 0
Watts Bar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 6 Given the follow in g p lant conditions
- Unit1is operating at 100%po wer.*TheComponentCo
o ling System (CCS)is in its norma l full power alignment.
Whichof the following indica tionsi s abnormal and requires changing plant condi tions t o c o mpensatefort he condition?A.#4RCPThermal Barr i er Flow-40 gpm.B.#4 R CP Lowe rOilCoo ler Flow-9 gpm.C.1AES F Header Supply Flow-1500 gpm.D.1BESFHeader SupplyFlow-5500gp m.6 of 1 00
WattsBar Nuclear Plant2008InitialLicense
Written Exam SENIOR REACTOR OPERATOR QuestionNumber:7 Gi ven the follow ing plant conditions:*A powe r esc a lati o n isinp rogres s.*P l ant i s currently h olding powerat30%foras econdary chemistryho
ld.*P r essurizer Pr e ssure Channel Sele ctor Switch 1-XS-68-340D isinthe"PT-68-340&33 4" position.*Pr essurizer Pressure Transm itter 1-PT-68-340 fails HIGH.(1)What action i s required to stabilize RCS pressur eatits normal value?AND (2)I f thatac t io n wa s u nsuccessful , w hat w ill ensure t h atadequatedepartu re from nucleat e bo ilin g rati o (DNBR)i s maintained?A.(1)Manually increasingthe
master controller
output.(2)Automatic Reactor tripwhenP r essur izer pressure lowerstoSI initiation
s etpoint.B.(1)Manually increasingthe
master controller
output.(2)Automat ic ReactortripwhenPressurizer pr essure lowerstoRPStri p setp oint.C.(1)Manually decreasingthemastercontroller output.(2)Automatic R eactor tripwhenP re ssur i zer pressure lowe rstoS I initiati on setpo int.D.(1)Manually d e creasing the mastercontroller output.(2)Autom atic ReactortripwhenPr
essurizer pressure lowerstoRPSt rip setpo int.7 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 8 Giventh e followingplantcond itions:*A steam generatortub
e rupture isinprog ress.*Th e Chemistry L ab h as just informedthecrewth attheactiv ity levelsin#1SGar e high , and thatsamplev alueshavebeen confirmed.*Thecrewis
implementingE
-3, STEAM GENERATOR TUBE RUPTURE.Asaresultofactions dire ctedbyE-3,whi chONEofthe following requiresentryintoaTechnical Specification
Action statement?
A.Adjustingth
e#1SGPORVcontroll
er setpointto90%.B.Closing the#1SG MSIV.C.Closingth eTOAFWpumpst
eam suppl y val vefrom#1SG.O.C oolingdowntotargetincore
temperatu reof479°Fatthema ximum rate.8of100
WattsBar Nuclear Plant2008InitialLicense
Written Exam SENIOR REACTOR OPERATOR QuestionNumber:9 Given th e followingplant conditions:*Unit 1 is initiallyi n Mode 3 pr epar ing for a reactor startup.*As team leak dow nstreamofthe MSIV s r e quir ing safety i n jection has occurred.*Operatorsare unable to close any MSIV from the Control Room.*Th e applicable
EOP has d irect ed MSIV cl o sure.*Attempts t o isolate a n MSIV f rom th e AuxiliaryControlR oom h ave been unsucce ssful.Which ONEofthe following d e scribes: (1)Theactions required byth e pro c edure i n e ffec t , AND(2)When that action has been taken , howwillthe control room operator know it was s uccessful?A.(1)Dispat ch operator to locally isolateand bleed off the contro lairtothe MSIVs.(2)Require s lo cal verification
of MSIV cl osure.B.(1)Dispat ch operatort o l o c all y isolateand bleedoffthecontrol air t o th e MSIVs.(2)Main control room oper ator not es GREEN light above MSIV controlswitches i s LIT.C.(1)Dispatchoperatortoatt
empt MSIV closure b y pulling co ntrol power fuses.(2)Requ ires lo cal ver ification of MSIV closure.D.(1)Dispatch operator to attempt MSIV closurebypull ing control power fuses.(2)Main control room operator notes GREEN light above MSIV controlswitchesisLIT.9 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 10 Unit 1isi nMode3followingalo ss of offsitepowe
r and thefailure of bothth e Unit1diesel generatorstost art.WhichONE ofth e following id entif ieshowtheMCRcreww
ill mon itorCoreE xit Thermocouples
andth e effectonth e postaccidentmonitoring(PAM)instrumentationTechSpecLCOfo r Core Exit Temperature?A.Plasmadisplaysonthecontrolboard
.PAMTechSpec
LCOentryisrequired
.B.Plasmadisplaysonthe controlboard
.PAMTechSpec LCO entry isNOTr equired.C.Integrated C o mputer System(ICS)since theplasma display sonthecontrol boardwill be unavailable.PAMTechSpecLCO
entryisrequired.D.IntegratedComputerSystem(ICS)sinc e th e plasma displays onthecontrolboardw ill be unavailable.PAMTe ch SpecLCOentryisNOT required.10 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 11Giventhe following plant condit ions:*Unit1isat100
%power.*Al arms re ceived indicatethatan electricalboardhasfailed
.*Alltripstatusl
ights ar eOFFon PaneI1-XX-55-5(on1-M-5).Whi chONEofth e following identifies(1)whi ch e lectricalboardfailedand(2)thereasonth
at manipulation
of controls inthe AuxiliaryControlRoom(ACR)is
required?(1)A.120VACVital
Instrument
Board 1-1.B.120VACVital
Instrument
Board 1-11.C.120VACVital
InstrumentBoard1-1.D.120VACVital
Instrument
Board 1-11.(2)ACR Auxiliary Feedwater ControllersforS/G 3and4have swapped to MANUALandrequire
adjustment
to ensure an operableheatsinki s maintained
.ACRAuxiliary Feedwater ControllersforS/G 1and2have swapped to MANUALandrequire adjustment
to ensure an operable hea t sink is ma intained.1-FCV-62-93 and 1-FCV-62-89havefailedOPENand related controlsmustbetakentotheAUX position to reestablish
charging andRCPsealflows.
1-FCV-62-93
and 1-FCV-62-89havefailedOPENandrelated
controlsmustbetakentotheAUX position to reestab lish charging andRCPsealflows
.11 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 12 G i venthefollow ing pla nt conditions:*Unit1i sat100%powerwithnoTechSpec
LCO Actionsin effec t.*The125VD C PowerS ystemisnormallyalignedwiththeexce
pt ionofthe6-S Vital Battery Chargerbeingalignedtot
he 125v Vital Battery Board IIdueto sch eduled maintenanceonthe 125v V ita l Charge r I I.*O ffs ite power islost.*A ll dieselgeneratorsst artandloadexceptforthe 2B-B diesel generator whic h FAILS t o start.Whi ch ON Eofthe following identifies
the condition of the125V Vital DC batteries I I and IV?(AssumeNOop
erator act ion is t aken.)A.Battery IIisbeing maintainedatnormal voltage.BatteryIVi s discharg ing.B.B attery IVis beingmaintainedatnormal voltage.Battery I Iisdischarging.C.B oth batt eriesareb ei ng maintainedatnorma l voltage.D.Bothbatteries ared isc harging.12o f 100
WattsBar Nuclear Plant2008InitialLicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 13 G i venthefollowing plant conditions:*TheUn it isat100%power.*ERCW systemisinnormal
alignment.
- ERCW headers1Aand2Aareind
icatinglowflow.*The following MCR alarms are LITon1-M-27 A:*Window 223-A,"ERCWHDRASUPPRESSLO".*Window 223-C,"ERCWHDR 1 A STRAINER 6 P HI".*Window 223-B,"ERCWPMPA-A Discharg e Pressure Low".*Window226-B,"ERCWPMPD-ADischarge Pressur e Low".WhichONEofthefollowing
descr ibeswhathas occurredinthe1A ERCW h eader?A.Supply headerhasruptured
intheAuxiliary Build ing.B.D ischarge header has rupturedintheAu xiliary Bu ilding.C.Supply heade rhasruptured
upstreamofthe1Ast rainer.D.Supply h e aderhasrupturedbetween th eIPSandAu xiliary Bld g.13 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 14 Complete the following statement:
The reason a backup nitrogen supply is providedtotheSG PORVsisto ensure that during___(1)the crewhasthe capability
to operatethemfora minimum numberofcycles,andthe alignment is initiated (2)_ill 11l A.an AppendixRFire automaticallyonlow control air pressure.B.aLossof Offsite Power manually.C.an AppendixRFire manually.D.aLossof Offsite Power automaticallyonlow control air pressure.14 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 15 When performing
ECA-1.2, LOCA OUTSIDE CONTAINMENT, why are RHR components
addressed BEFORE other ECCS components?A.To maintain suction to CCPs if containment
sump swapover has already occurred.B.This allows the CCPs to maintainRCPseal injection.
C.Isolation of RHR components
requires manipulations
outsidetheMCR.D.Theleakis
most likely to occurinthe RHR system.15 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 16 Given the following plant conditions
- ALargeBreak
LOCA has occurred.*Containment
pressureis10.5 psig.*RWSTlevelis20
%.*Containment
sump levelis68%.*1ARHRpumptrippedduetosevere
damagetoitsmotor.
- 1-FCV-63-73, CNTMT SUMPTORHRPMPB SUCTfailedtoopen
automatically
and attemptstoopen i t manuallyhavefailed.WhichONEofthe
following describes the proper alignmentofthe ContainmentSpray(CS)pumpsforthee
xisting plant conditionswhiletheCSpumps
suction is alignedtotheRWST?
A.StopbothCS
pumpsandplacethecontrol
switches in P-T-L (Pull-To-Lock).B.StopbothCSpumpsandplacethecontrol
switches in A-Auto.C.StopONECSpumpandplaceitscontrolswitchinP-T-L (Pull-To-Lock).D.StopONECSpumpandplaceitscontrolswitchinA-auto.16 of 100
WattsBar Nuclear Plant2008InitialLicense
Written Exam SENIOR REACTOR OPERATOR Question Number: 17WhichONEofthe
followingisan adverse consequence
of delayingbleedandfeedcoolingifthe
conditions
for initiatingbleedandfeedaremetinFR-H.1,"Response toLossof SecondaryHeatSink"?
A.Anover pressure challengetothereactorvessel.
B.InabilitytorefilltheS/Gs
withoutdamagefromhighthermalstresses.
C.Inabilitytoprovide sufficientinjectionforcorecoolingpriortocore
uncovery.D.Steam formationinthehotlegswill
accelerate
the degradationofnatural circulation
flow.17 of 100
Watts Bar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 18 G iven the following conditions:*Pl ant i sat100%power.*All systems normally aligned.*TheTr ansmission
Oper ator has notified the plant that system grid voltageishighand forecastedtogoh igher.Ifthe Transmission
Operator requests the plant t otakeinthe maximum value of MVARstohelp stabilizethegrid, whatisthe maximum allowed MVAR incoming value, and howisthe adjustment made in accordance
with 1-PI-OPS-1-MCR, Main Control Room?A.B.C.D.MAX INCOMING VALUE 100 MVARs 100 MVARs200MVARs 200 MVARs METHOD OF ADJUSTMENT
E xciter Voltage Adjuster E xciter Base Adjuster E xciter Voltage Adjus ter E xciter Base Adjuster18of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 19Giventhe following plant conditions:*Unit1isat50%power.*RodcontrolisinAUTOwithBankDat176steps.*Tavg auctioneeringunitfailsLOW.*BankDgroup2step
counterfailstomove.Asaresult,rodswill
__(1)__andtheBankDcontrolrodCERPI
indicationsmustbe matched within_(2)__.(1)(2)A.Insert+/-12stepsofeach
other (highest to lowest rod).B.Insert+/-12stepsoftheoftheGroup1stepcounter.
C Withdraw+/-12stepsofeach
other (highest to lowest rod).D.Withdraw+/-12stepsoftheoftheGroup1step
counter.19 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 20Giventhe following plant conditions:
- 1-XS-68-339EPRZLVLCTRLCHAN
SELECTisinthe 339/335 position.*Withactual
pressurizerlevelat50%,1-L
T-68-339 Pressurizer
Level Transmitter
develops aslowleakinthe
reference leg.What IStheeffecton
Pressurizerleveland charging flow?A.Actuallevelinthe
Pressurizerwillbe increasing, causing chargingflowtolower.B.Actuallevelinthe
Pressurizerwillbe decreasing, causing chargingflowtorise.
C.Indicatedlevelon 1-LT-68-339willbe increasing, causing chargingflowtolower.
D.Indicatedlevelon1-L
T-68-339willbe decreasing, causing chargingflowtorise.
20 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 21 Which ONEofthe follow ing describes the Reactor Protection
System responsetoalos s of control power versusalossof instrument powertoN-31 Source Range Monitorwiththe"TRIP BYP ASS SWITCH"inthe"BYPASS" position?Control Power Loss Instrument
Power Loss A.Reactor tripNotrip B.Reactor trip Reactor tr ip C.NotripNotrip 0 N o trip Reactor tri p 21 of 100
WattsBar Nuclear Plant2008InitialLicenseWrittenExam
SENIOR REACTOR OPERATOR QuestionNumber:22 Given the following plant conditions:
- Operators are respondingtoan unexpected
annunciator, 182-B tlTB SUMP DISCH O-RM-212 L10 RAD HI.*The station sump pumps discharge is currently alignedtothe Low Volume Waste Pond.Which ONE of the following identifies
the effectthehigh radiation condition hasonthe Station Sump pumps and how the pumps'discharge should be alignedasa resultofthe alarm in accordance
with AOI-31, Abnormal Release of Radioactive
Material?Effecton Station Sump Pump Station Sump Pumps Discharge Aligned to A.Pumps stop Unlined Chemical Holdup Pond automatically.
B.Pumps stop Lined Chemical Holdup Pond automatically.
C.Requires operator action Unlined Chemical Holdup Pond to manually stop pumps.D.Requires operator action Lined Chemical Holdup Pond to manually stop pumps.22 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 23Ifalocalfirepanelhasa
TROUBLElitafterbeingreset
,whichONEofthe
following identifieshowthemaincontrolroompanel (O-M-29)will indicate a subsequent
troubleANDafirealarmonthesamelocalpanel?
Subsequent
Trouble A.Wouldbeindicated.B.Wouldbeind
icated.C.Wou ldNOTb e indicated.D.WouldNOTbe
indicated.AlarmTroubleconditionwouldclear,Alarmwouldbe indicated.Troubleconditionwouldmaskalarm
cond ition.Trouble condition would clear , Alarmwouldbe indicated.Trouble conditionwouldmas k alarm condition.23of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 24Alargeb reak LOCAisin progress.Which ONE ofth e f ollowingidentifies conditionsthatreq uire entryinto FR-Z.1 High Cont a inment Pr e ssure?Containment
Pressure Containment
Spray Pumps A.3.0psig No pump s ru nning B.6.0 psig1pum p runn ing C.9.0psig1pum p runnin g D.1 2.0 ps ig 2 pumps run n in g24of100
.......WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 25Unit1isat100
%power.WhichONEofthe
following i s the HIGHESTofth e belo w listedvalues f or Dose Equivalent Iodine-131(1-131)without requiringentry into th e Acti on Statement f or LCO3.4.16 , RCS Specific Activity?A.0.1
B.0.2
C.0.3
D.0.425of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATORQuestionNumber:26Giventhe following plant conditions:*TheUnitwasatfull
powerwhenaSmall
Break LOCA occurred.*Thecrewhas
transitioned
to ES-1.1,"SI TERMINATION."*The crew has just stoppedoneofthe charging pumps.Whatisthe reason for checking RCS pressure stableorrisingatthis
point in ES-1.1?A.To determineifthe residual heat removal (RHR)pumps should be secured.B.To confirm that a secondaryheatsinkis
required.C.To confirmthatflowfromone
chargingpumpis adequate to maintain pressure.D.To determineifthe safety injection (SI)pumps should be secured.26 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 27 Given the follow ing plant conditions:*Areact or trip concurrent
w ithalossofoffs
ite power has occurred.*Thecrewh as entered FR-H.2, Steam G enerator Overpr essur e based onaYELLOW conditi o n on the Heat Sink CSFStatus Tree.*#2 SG pressure is1230 psig.*#1 ,#3,and#4SGpressures ar eat1 210 psig.*#2SGleve lis85%a nd slowly ris ing.*#1,#3 , and#4SGlevelsare65%andslowly rising.WhichONEofthef ollow ing actionswillmitigatetheSGov erpressure
condition?A.Initiate blowdownflowfrom#2SG
.B.Openthe condensersteam dumps.C.Open the steam supply t o the Turbin e Driven AFW pump.D.Initiateminimum AFW flow to#2 SG.2 7 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 28 Which ONEofthe following failures assoc iatedwithRCS flow transm itters causes a reactor tr ip s ignal?A.A single high pressure tap fails when operatingat50%reactor power.B.As ingle low pressure tap fails when operatingat50%reactor power.C.Two high pressure taps fail when operatingat5%reactor power.D.Two low pressure taps fail when operatingat5%reactor power.28of100
- ...':'.=-'.0_-,"__*****._._**WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR QuestionNumber:29 On a rising VCTlevelthe Divert Valve is designed to...A.fullyopenat6 3%andfully closewhenlevel has loweredto41%.B.begin modulating
openat63%andiflevel
continuestorise,willbefullyopenat93
%.C.fullyopenat93
%andwillbegin
modulat ingclosedwhenlevel
dropsto63%.D.begin modulatingopenat41%andwillbefullyopenwhenlevel
reaches 63%.29 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 30 Gi venthefoll owing plant conditions
- TheplantisonRHRcoolingfollowinganaturalc
irculation
cooldown.*RCStempe rature is 15 0°F.*Pressurizerpressure is340psig.*Pressurizerlevelis 2 5%.*Preparations
fo r return ingtoMode4are
i n progress.In accordancewithSOI-68
.02, Reactor CoolantPumps,whichONEofthe
following requires a n actionplant o be developedw ith Reactor Engineeringpriortostart
ingthefirstRCP?
A.Shutdownandcontrolrodshavebeen
withdr awn5st eps to ensurenotherm al bindi ng.B.Pressurizer
boron concentration
is45ppmle ss thanRCSboron.C.Steam Generator m etal temperature
is105°F.D.AnRCSb o rationoccurredduringthecooldown.30of100
WattsBar Nuclear Plant2008InitialLicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 31 Gi ven the following plant conditions
- Plant startupisin progress.*During performanceofGO-1 , Unit StartupfromCold ShutdowntoHot Standby , the CLA isolat ion valves were left CLOSED with poweronthe valves as pressurizer
pressure w as raisedfrom900psigto1900psig
.*A manual safety inj ection (SI)i s initiated.WhichONEofthe following identifies
the positionofthe CLA isolat ion valves beforetheSI i s initiated and how the MANUAL Safety injection will affectthe valves?Before 51 A.Valves w ill have automatically
opened.B.Valves will have automatically
opened.C.Valveswill have r emain ed clo sed.D.Val ves w ill have remained closed.Effectofthe 51 signal An open signa l w ill be generatedtothe valves.An open signal will NOT be generatedtothe valves.Anopen signalwillbe generatedtothe valves.Anop en signal will NOT be gene ratedtothe valve s.31of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATORQuestionNumber:32
Given the following plant conditions:*The plantisat100%power.*Annunciator88CPRT PRESSHIis received.*PRT pressureis8.5psigand
RISING SLOWLY.*PRTlevelis67%and
STABLE.If allowed to continue, whichONEofthe following describes(1)the LOWEST PRT pressure atwhichthe rupture disc operates,AND(2)the action required to restore PRT pressure?A.(1)50psig.
(2)VentthePRTtothe
Waste Gas Header.B.(1)85psig.(2)VentthePRTtothe
Waste Gas Header.C.(1)50psig.
(2)DrainthePRTtothe
RCDT to reduce level and pressure.D.(1)85psig.(2)DrainthePRTtothe
RCDT to reduce level and pressure.32of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 33 Given the following plant conditions
- TheUnit isat100%power.*1-M-27C.Annunciator
249A"U1 SURGE TANK LEVEL HI/LO"isin alarm.*TheCRO reports that Surge Tanklevelis73%onboth 1-L1-70-63Aand1-L1-70-99Aand
le vel is rising.*TheCRO reports that 1-LCV-70-63 , U1 SURGE TANK MAKEUP LCV , is closed.-1-FCV-70-66AU1Surg e T ankVentis closed.-1-PT-70-24A,CCSHXASUP PRESS, ind icates100psigand
stable.-All systemsarein normal operational
alignment.Forthe above cond itions,aleak i n whichONEofthe following components
accounts forthe above cond itions , and whatisthe effect of isolating that component?A.RCS Sample heat exchanger.
SuspensionofRCS sampling which leadstotheinab ility to determineifRCS chemistry limitsaremet.BRC P s eal w a terreturnheatexchanger.Manual isolationofRCP sealreturnline
resultsinliftingoftheseal
return reliefvalvetoth e PRT.C.CVCSletd ownheate xchanger.Manual isolation of normal letdown flow resultsinlossof cleanup and leads to exceed ing RCS chemistry limits.D.RCP thermal barrier.M anual i s olationofthe thermal barr ier heat exchangers
resultsinlift ingofthe relief valve.33 of 100
WattsBarNuclearPlant2008InitialLicenseWrittenExam
SENIOR REACTOR OPERATORQuestionNumber:34Giventhefollowingplant
conditions:*Unit1at100%power.
- 1-SI-68-901-A,ValveFullStrokeExercisingDuringPlant
Operation:
ReactorCoolantTrain,isinprogress.
- 1-FCV-68-333A,BlockValveforPORV340A,hasbeenclosedandthestroketime
recorded.*Whentheblockvalveisreopened,an
increaseisseeninPRT
pressure and temperature.WhichONEofthefollowing
identifiesaconditionthatwillcausethe
changeinPRT conditionsandtheactionrequiredin
accordance
with 1-SI-68-901-A?
A.APORVopenedduetotherapidpressureRISEbetweenthePORVandtheblockvalvewhentheblockvalvewasreopened;PlacethePORVcontrol
handswitchtoCLOSEpriorto
openingtheblockvalve,thenreturntoAUTOaftertheblockvalvehasbeenopened.B.APORVopenedduetotherapid
pressureRISEbetweenthePORVandtheblockvalvewhentheblockvalvewasreopened;PlacethePORVBlockValvecontrol
handswitchtoCLOSE.C.ThePORVopenedduetothe
pressure REDUCTION which occurredbetweenthePORVandtheblockvalvewhiletheblockvalvewasclosed;PlacethePORVcontrol
handswitchtoCLOSEpriorto
openingtheblockvalve,thenreturntoAUTOaftertheblockvalvehasbeenopened.D.ThePORVopenedduetothe
pressure REDUCTION which occurredbetweenthePORVandtheblockvalvewhiletheblockvalvewasclosed;PlacethePORVBlockValvecontrol
handswitchtoCLOSE.34of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 35Giventhe following plant conditions:*Theunitisat
100%power.*Pressurizer
Level Control is selectedto1-LT-68-339/335
on 1-XS-68-339E.If1-L T-68-335failslow, whatisthe impactonthe Pressurizer
Pressure/Level
Control System?A.Pressurizer
Heaters de-energize
and Letdown isolates.B.Pressurizer
Heaters de-energize
and Letdown does NOT isolate.C Pressurizer
Heaters remain available and Letdown isolates.D.Pressurizer
Heaters remain available and Letdown does NOT isolate.35 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 36 Given th e following p lant conditions:*Theplantisoperatingat100%power.*Annunciator 11 4-A, G ,t:t;JERAL
WARNINGisLIT..sWh ichONEofthe follow ing(1)l istsaconditionthatwill causetheal armand(2)describes wh at indicationthe operatordispatched locallywilluse t o d et ermine th e cause o f th e alarm, in accordancewithth
e ARI?(1)A.ReactorTripBypass BreakerAis rackedi n.B.Bl own G round Return Fus e.c.Reactor Tri p Bypass BreakerA i s r a c ked i n.D.Blown Ground Return Fuse.(2)Board-ed ge LED lightsonthe
Semi-Automatic
Tester.Board-edge LED lightsontheS emi-Automat ic Tester.Status Lightsontheoutsideofth
e Local Panels.Status Lightsonthe outsideoftheLocalPan
els.36 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OP ERATOR Question Number: 37Giventhe following plant conditions
- An inadvertent
Safe ty Injec tion (SI)hasoccu rredonUnit1 ,andthecrewis
terminating
t he Safety Inj ection.*T he OAChas pressed the SIResetpus hbuttons.Assumingn o additional
operator a ction ,whatisthesta
tusofthefollowing ESFsigna ls?Low Steam Line Pressure Automatic SIMainSteam Isolation S ignal A.Enabled DisabledB.Dis abled En abledC.Disabled Disabled D.Enabled Enabled 3 7 of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 38 Given the following plant conditions:*Ama in ste am line rupturehaso c curred insidecontainment.*Containm ent pressurepeaked at3.6 psig.*A ll e ngi nee redsafetyf e atures h a veactuatedperdesign.Whatisth e e xp ected statusofth e conta inment Upper Compartment
Cooling Fans (UCCF)and Low er Compartment
Cooling Fans (LCCF)10m inutes afterthe event?UCCF LCCF A.Running Tripped B.Tripped Running C.Running RunningD.Tripped Tr ipped 38 of 100
WattsBar Nuclear Plant2008InitialLicense
Written Exam SENIOR REACTOR OPERATOR Question Number: 40Whileperfo
rming ES-1.3 TransfertoConta inmentSump,the Containment
Spray Pump hand switches are requiredtobeplacedin
Stop-PULL-
TO-LOCKatwhichONEof
the following setpoints?A.ContainmentSumplevel rises t o 8 3%.B.ContainmentSump l e v el rises t o 3 4%.C.Refue ling Water StorageTankleveld
ropsto16.1%.D.Refueling Water StorageTankleveldropsto8
%.40 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 41Giventhe following plant conditions:*AtEOL , a reactor startup is i n progress following a 6-day outage.*The Reactor Engineer has providedanECPwhich
predicts the reactor goingcriticalat1
20stepsonControlBankD.WhichONEofthe
following conditionswillresultinthecrit
ical rod height being HIGHER thanthevalue predictedbytheECP?A.A d i l u t iono f 500gallon s isp erformed.B.Feedwaterflowis increasedtoallSGsduetoa
controller
malfunction
.C.St eam Dump Controller
1-PIC-1-33
fails , resultingina pressure decreaseof50psig.D.An improperly performedstepinthePost
Maintenance
Test procedureresultsinthe
closureofallMSIVs.
41 of 100
[.-......WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 42 G iventhefo llow i ng plant conditions:*Theunitisat100
%power.*Unidentified lea kageis0.0 3 gpm.*Steam Generator#3 has a 17gpdtub e leak.*AOI-33 , Steam Generator Tube Leakage, AppendixAfor Steam G ener ator Tub e Le ak Monitoring,i s inprog ress.*Subsequently,theactivityintheRCSin
cr eased significantlyduet
o fu el failures.NOTE: Radiat ion Mon itor Id entification Numbe rs: 1-RM-90-10 6-Lower Cont a inment R ad iation M onitor 1-RM-90-119
-Condens er VacuumPumpE xhaust 1-RM-90-423-#3 Steam Line Radiation Mon itor Which ONEofthef ollow ing descr ibes how 1-RM-90-106and 1-RM-90-423
will respondasa r esultofthefai led fuel without a change inthe amount of steam generatortubeleakage an d the action directed i n AOI-33 , Appendix A ,forus ing rad iation mon itors to quant ify tub e leakage?RAD Monitor ResponseA.1-R M-90-106 an d 1-RM-90-423 increase.B1-RM-90-1 06and 1-RM-90-423 increase.C.1-RM-90-106 rema ins constant.1-RM-90-42
3 in creases.D.1-RM-90-106 remains constant.1-RM-90-423 increases.Action to Quantify Recal culate valuesfor correlating
1-RM-90-119 t oSGtube leakage.Stopusing 1-RM-90-119asthe pref erred indication
fo rSGtubeleakrate
monitoring
.Recalculate
va lues for correla ting 1-RM-90-119toSGtubeleakage.Stopusing1-RM-90-119asth
e pr eferr ed indicat ionforSGtubeleakrate
monitoring
.42 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 43 Giventhe follow ing plant conditions:*Th e Unitisat50%load,steady state.*All Feedwater valves/pumps
are i n automatic.*BothMain Feedwater Pumpsarerunn ing.*Standby Feed P umpisoffwithits control handswitchin"auto".*T he controll in g steamflow (SF)transm itt er on#1S/G fa ils LOW.Whi chONEofthefollowing des cribes the responseofthe Feedwater Control Systemtothe g i v en condi tio n s?A.MFPspeedRISES
- 1S/G Feedwater regulating valve closes initiallytomat
ch feedwat erflowtoth e fa iled SF input.B.MFPspeedRISES
valve closes initiallytomatch
f eedwaterflowtothefailedSFinput.
D.MFPspeed LOWERS;#1S/G Feedw ater regulating
va lve closesinitiallyduetothele vel errorsignalpresent.43of100
Wa tts Bar Nuclear Plant 2008 Initial License Written Exam S ENIOR REACTOR OPERATOR Quest ion Number: 44 Given the following plant conditions
- Theun it is at100%power.*The TO AFW pu mp is out of servicetorepair theT rip-and-Thrott le valve linkage.*6.9 KV ShutdownBoard1Btrips due toa differential
relayac tuation.*An inadvertent
Safety Injec tionoc curs.Which ONE of thefollowingdescribes the SGsthatarereceiving A FW flow andwh ich SG bl o wdo wn is o lation va lvesare closed,asaresu
lt of the above conditions?
(Assum e nooperatorac t ion.)A.B.c.O.SGs Receiving AFW flow On ly S G1and2 OnlySG1and2 Onl ySG1 an d 3 OnlySG1and 3 SG SLOWDOWN Isolated AL L SGs Only SG 1 and3 Only S G1and2 AL L SGs 44 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 45Giventhe following plant condit ions:*Th e unit isat100%power.*All secondary condensate
and feedwaterpumpsarein
service.*The1DUn it Board developsafaultandtrips du etorelay operation.Whi ch ONE ofthefo llowing pumps i s lostasaresultofth
is failure?A.1BHotwellPump.
B.1A Conden sate Booster Pump.C.1B#3 Heater Dra in Tank Pump.D.StandbyMainFeedPump
.45 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 46 Given the following plant conditions:*1A-A a nd 1 B-B SI Pumpb reakersare" Racked Up".*Afuse blows inthe NORMALDCTrip circuitforthe 1A-A SI Pump.*A safety injection(SI)actuation occurs.Which ONE of th e f ollow ing d escrib esther esponseofth e SI Pumps totheS I signal?A.1B-BSI Pumpwilla utostart,but 1A-A SI Pumpwillnotautosta
rtuntilthe control power supply i s transferred.B.1B-B SI Pumpwillauto start ,but1A-A S I Pumpwillnotauto
start and must be startedfromtheM
CR handswitch.C.BothSI Pumps will auto start , but 1A-ASI Pump cannot be stoppedfromthe MC R D.Bo th SIPumps willautostart,but
1A-ASIP ump willimmediatelytripdu
etotheb lown fuse.46of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR QuestionNumber:47WhichONEofthefollowingisthe
power supplyforthe2A-ADiesel
GeneratorFuelOilPriming
pump?A.480vACfromDiesel
Generator AuxiliaryBoard2A1-A.
B.480vACfromDiesel
Generator Au xiliaryBoard2A2-A.
C.125vDCfromthe125vDCVital
BatteryBoard2-1.D.125vDCfromthe125vDC2A-ADieselBattery
Distribution
Panel.47 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 48 Aft erareactortripandsafety injectiononUn it 1 , the following conditions
are observedfor1A-A D iesel Generator (DG):*1-M-26A , Window 198A ,"DG START/RUN FAILURE"alarm-LIT.*Gre en"DGRun"light
-ON.*Red"DGRun"light-OFF.*Red"DG Above 40rpm"light-ON.*Diesel Generator 6.9KVbr eaker-OPEN.*Diesel Generator voltage-ZERO.Fromtheaboveindications
, the operatingcrewknowsthat
1A-A Diesel Generatorstartedand
A.shutdown after 10 seconds.B.enginespeeddidnotriseabove550rpm
.C.engin e sp eed e xc eeded550rpmbutdidnotriseabove
850rpm.D.shutdownduet o i nsuffici ent air intherecei ver.48of100
-.0*":'-*..WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR QuestionNumber:49 The Turbin e Bui lding NAU O h as pl a c ed 1-HS-1 5-44 , SG Blowdow n Dis chtoCTBD , (Cooling Towe r Blowdown), in OPEN per SOI-15.01, in ordertodir ectSGBDflowtoCTBD
.WhichONEofthe follow ing w ill occur ifradiat ion monitor 1-RM-90-120 losesflowthroughthe
monitor?A.Blowdown willbe isolatedtoth
eCTBDresultinginlossof blowdown flow.B.Blowdownwillbe isolatedtotheCTBDand
automat ically be redirectedtothe condensate header.C.Bl owdownwillcontinuetoth eCTBDbutwillisolateif1-RM
-90-121reachedth eHIRAD setpoint.D.Blowdownwillcont inuetotheCTBDa
nd w ill NOT isolate if 1-RM-90-121
reachedtheHI RAD setpoint.49of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 50 Gi venthefo llowing plant conditions
- Unit1 experienced
a Reactor Trip/Safety
Injectionduetoa LOCA ins ide containment.*When checking annunc iators followingthetr ipandSI ,theCROnotesthatthefollowing annunciatorsareinalarm:
o 173B , LWR CNTMT AIR 1-RM-106RADHI.o 173E, LWR CNTMT AIR 1-RM-106 INSTR MALF.Assum ing all componentsrespondas designed, wh ichONEofthe following actions wi ll theNAUOtakeduetotheabove
conditions
?A.Reopentheradiat
ion monitor isolationvalvewhich
restores flow through the monitor torestoreTechSpec
operabil ity.B.Restartth e radiation monitorpumpwhich restores flow through the monitortorestoreTech
Spec operability
.C.Stopthe radiation monitorpumpto prevent damagetothepumpduetothe
monitor be ing isolatedasaresultofthe
safety inject ion.D.Closethe
radiation monitor isolationvalvestoiso
late mon itorduetothepumpbeingtripped
as aresultofthe
safety injection.
50 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Quest ion Number: 51 Reactor tripa nd safetyinjection signals have b een manually initiated.Which ONEofthe following describes the required pos itionsforthe listed ERCW valves in accordance
with E-O , Appendix A.Equ ipment Verification?O-FCV-67-144,O-FCV-67-152,"CCS Heat Exchanger'C'"CCS Heat Exchanger'C'Disch to Hdr A" Alt Disch to Hdr S" A.CL OSED OPENtoPos it ion A 8 THR OTTLED CLOSED C.THROTTLED OPENtoPosition A D.OPEN CLOSED 51 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Quest ion Number: 52Giventhe followingplan
t con ditions:*T he p lant is operatingat100%power with1BCCP inservice.*The Control Room Operator shutdownsdowntheC-A
ERCWpumpin preparation fora testonthe 2A 6.9 KVShutdown Board.W hich ON Eofthe following descr ibe stheimpa ctofsh utting d ownthepumpo n the listed par ameters?(Assumenoother operatoraction.)18CCPOil Seal WaterReturnHeat
Temperature
Exchanger Temperature
A.Rises Rises B.Rises Remainsconstant C.Remains constan t Rises D.Remains constan t Remains const ant 5 2 of 10 0
WattsBar Nuclear Plant2008InitialLi
cense Written Exam SENIOR REACTOR OPERATOR Ques tion Number: 53 Which ONE o f thefollowing identi fies b oth ofthe following?(1)The lowestoft he listed contai nment pressures th at resultsin1-FCV-32-80, Au x Airto Rx Bldg Train B , being automatically
is olate d , and(2)T he lowest o f thelistedair pressures sensed downs tre am of the valve tha t allows the valvet o RE MAIN OPEN afterthevalvew as opened an d th e controlswitchon 1-M-15 placed to A-Auto after th e isola tion signalwasreset.ill ill A.2.0p sid68psig B.2.0 ps id 78psig C 3.0psid68ps ig D.3.0 psid 78psig 53of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 54 G iven thefollowingplant
condit ions:*PlantisinMode4.*Lower c onta inment airlock isb roken and innerdoor is jamm ed an d wi ll notopen.If conditionsw ere t o requireanemergencyentryinto lower containm entbyop eningthe hatch , whichONEofthe
followingis REQUIREDtobe contacted priortoopeningthesub-hatch , andwhataction isrequired asa resultofthesub-hatchbe
ing open ed?A.ShiftManager;Perform 1-SI-88-24 , Containment
Divider Barrier P ersonnel Acce ss Hat ches&Equipment Hatches.w ithinone(1)hour.B.Sh ift Manager;Perfo rm 1-SI-88-24, Containment
Div ider Barrier Personnel Acce ss Hatches&Equipment Hat ches.prio r t o Mode 3 entry.C.Work WeekManager;Perf orm 1-SI-88-24, Containment
Div ider Bar rier P ersonnel Access Hatche s&Equ ipment Hatches.w ithinone(1)h our.D.WorkWeek
Manager;Perform 1-SI-88-24 , Conta inment Divider Barrier Pe rsonnel Access Hatches&Equ ipment Hatches , priortoMode3 entry.54of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 55WhichONEofthe
following identifies
the NORMAL pre ssure band controlledbythe Containment
Annulus VacuumSystemandtherequired
method of controllingpressureif1-M27B Window 232-B, ANNULUS l1P LOIDAMPER SWAPOVERisLIT?Annulus Pressure Band A.-6.0to-6.2" WCB.-6.0 to-6.2"WC C.-4.3to-4.5" WC D.-4.3 t o-4.5" WC Method of Controlling
Pressure DispatchaNAUOtoRESE
T the dampers loca lly.Swapthe dampers using handswiches
on 1-M-27B.DispatchaNAUOto RESET the dampers locally.Swapthe dampers using handswicheson1-M-27B.55 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 56Giventhe following plant conditions
A.Availa ble B.NOTAva ilable C.Available D.NOT Availab le Actions ReguiredforRod Group alignmentUsethe"ALLRODS
" funct iononthe operating display.Flu xmapisrequiredtoconfirm rod position.Fluxmapis required to confirm rod position.Usethe"ALLRODS" functiononthe operating d isplay.56of100
WattsBar Nuclear Plant2008InitialLicense
Written Exam SENIOR REACTOR OPERATOR Question Number: 57 Wh ich ONE ident ifies BOTHofthe following for Hydrogen Recombiner
operations?
(1)Th e MA XIMUM Hydrogen Recombiner
t emperature
allowed when operating?
AND (2)The HIGHESTofth e listed containment
hydrogen concentrations
allowed when placing th e re combine r i n service?A.B.c.D.(1)Maximum Temperature(2)H2 Concentration
6%4%6%4%57 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 58 Followinga refueling outage ,thefollow ing cond itions exist:*Unit1 isinMode3prepa
ring fo r Mod e2entry.*Fuel shufflesarebeing conductedintheSp entFuelPit.*SpentFuelPoo
l CoolingpumpAistheon
ly SpentFuelPoolCoolin
g pump inservice.*The 2A-A ShutdownBoardnormalfeederbreake
r i s inadvertently opened durin g testing.*Th eDGstart s an d reenergizes the shutdown board.W h ich O NE ofth e f ollowi ng des cribes the i n itial effectontheSpentFuelPoolCooling system , andtherequiredaction,i f any , p er Spent Fu elPoolTech Specs?A.Th e SpentFuelCoolingPumpstripsfromtheboa
rd ,andthens equences bac kontothe shutdown board.SpentFuelPoolTechSpecs
requires that movement of irradiate d fuel assemb liesinthefuel storagepoolbe immediately
suspended.B.TheSp ent Fuel CoolingPumpstr ipsfromtheboard
,andth en sequences backontothe shutdown board.SpentFue l Poo l Te ch Specs does NOT require that movem ent of irradiatedfu
el assemblies inth efuelstor age poo lbesu spended.C.The Sp ent Fu el CoolingPumpstripsfromtheboard
, and remains off.Sp entFuelPoolTech
Specs requ ires that movement of irradiated
fuel assemblies
inthefuel storagepoolbe immediately
suspende d.D.The Spent Fue l Coo lingPumpstripsfromtheboard
, and remains off.S pentFuelPoolTech
Specs does NOT requirethatmov ement of irradiatedfu
el assembliesinthefuelstor
agepoolbe suspended.58of100
Watts Bar Nuclear Plant 2008 Init ial License Written Exam SENIOR REACTOR OPERATOR Question Number: 59 Which ON Eofthefollow
ing identifies (a)howmainsteam
header pressurerespondsa s turbin e loadisraisedfrom25
%to65%,and(b)which
methodofmainta
in ingTavgmatched with Tref res ultsinthevalueforMTCbe
ingtheMOST negative as turbineloadisraised
?A(a)Mainsteamheaderpressure lower s (b)Rodsa re withdrawn tomaintain Tavg on program,withBoronconcentrat io n held const ant.B.(a)Ma in steam header pressure r ises.(b)Rods arew ithdraw ntomainta in Tav g on program ,withBoron concentrat
ion h eld constant.C.(a)Ma in steam header pressure l owers.(b)Rodposition
isheldconstant ,whileBoronconcentrationisloweredtom aintain Tavgonprogram.D.(a)Main s team headerpressurerises.(b)Rodposition
isheld constant ,whileBoron
concentration
is loweredtomaintain Tavg on program.59of100
Watts Bar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 60 W h i chONE ofthef o llowing iden tifie s monitors associatedwi th Conde nser VacuumPump discharge wh ich ar ePostAccident Monitors(PAM),in accordancewith
SOI-90.05, Post Acc ident Radiation Monitors?A.Both 1-RM-90-11 9 and1-RM-90-404.
B.Ne ither 1-RM-90-11
9nor1-RM-90-404.C.1-RM-90-119isaPAM,bu t 1-RM-90-404
isNOT.D.1-RM-90-40 4 is a PAM ,but1-RM-90-119isNOT.60 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 61 W hi chONE ofth e follow ing occurs automatically
if the"8"MFPtripsduetothru st bearing wea r withthepl ant initiallyat100%power?(Assume no other equipment fa ilures.)A.T hemotordrivenAFWPumpsstart.
8.The Condensate
01pumpstripiff
eed waterflowdropsto<
80%.C.The"8"MFPT condenser condensate inlet and outlet valvesgo closed.O.Th e shortcyclevalve , 1-FCV-2-35
, modulatesopentodumpexcessivecondensateflo
w.6 1 o f 1 00
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 62 WhichONEofthe followingidentifiesa
condition that causes an instrument malfunct ion ala rm o n O-RM-90-122 , WDS Liquid release rad iation monitor ,andthe effecttheinstru ment m alfunct ion ala rm hasonvalve O-RCV-77-43,CTBLDNLNRAD
RELEASE CNTL?A.B.C.D.Cause of the alarmLossof signal from detectorLossofsign
al from detectorLossofflow
throughthemon itorLossofflow
through th e monitor Effect on O-RCV-77-43Autoc loses O-RCV-77-43ifthe valve was open.Prev ents O-RCV-77-43
from opening ifthevalve's l ocal contr ol handswitch
was placedtoOPEN.Auto closes O-RCV-77-43ifthe valvewasopen.Prevents O-RCV-77-43
f rom opening ifthevalve's localcontrolh andswitch wasplaced to OPEN.6 2 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 63Areleaseofthe
MonitorTankisin progress throughtheLiquid Radwaste System.WhichONEofthefollowing
conditions
directly results i n automatic closure of 0-FCV-77-43,Liquid
Radwaste Release Flow Control Valve?A.High radiationsignalon 0-RM-90-225, Condensate
Demineralizer
Release Liquid Radiation Mon itor.B.Riverflowdropstolessthan3500cfs
aftera1minutetime
delay.C.Cooling Tower Blowdownflowdrops below 25 ,000 gpm.D.SG Blowdown f low exceeds150gpm.63 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 64Giventhefollow
ingplantconditions:*Un it1is operatingatpower whencontrol airpressu restartstod rop.*Annunciator
42-F , SERVICE A IR PCV-33-4 CLOSED, alarms.*TheCROre sponds in accordance
w ith th e Annunciator
Response Instruction (ARI).WhichONEof
the following identifies
th e d ecreasing Control A ir system pressure that causes this alarmto occur and whethertheAu xiliary Aircompressorswouldhave
started iftheair pressure droppedlowenought
o causethealarm,butthen re covered without dro pping any lower?Pressure to Cause Alarm Aux Air Compressors
A.83psigWillhavestarted
B.83psigWillNOT havestarted
C.80 psigWillhavestarted
D.80psigWillNOThavestarted64of100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 65 Give n thef ollowin g plant conditions:*Unit1iscurrently at100%.*AfireoccursintheCable
Spreading Room.*The crewwasunabletostarttheHPFPpumps
.*The incident Commanderalsor eportsthatduetomultiple fire damper fai luresthefir e i s spread ing quickly.*Th ecrewhasenteredAOI
-30.2,FireSafe Shutdown.In accordan ce with AOI-30.2,whichONEofthefollow
ingfailuresresultsinalossofaControl
Function required toplaceth e PlantinHotStandby?REFERENCE PROVIDED A.Moto r DrivenAFWPumpsw illnotstart.B.RCS Thermal Barrier Boost erPumpstr ip.C.On e Ma in Ste amIsolationValve
failstoclose.DLe tdow n Iso l ation Valve1-FCV-62-69 failsclosed.
65 of 100
'::'.'"..,WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 66ForMode1 operation,whichONEofthefollow
ing descr ibes the MINIMUM number of Licensed Op erator positionstomanash ift,ANDthe MAXIMUM t ime requ i rementtorestoreifthe
minimum shift manning for Licensed Operatorsisnotmetper
OPDP-1, Conduct of OperationsandTechSpec5.2.2, Unit Staff?Minimum Shift ManningTimeRequirement
A.2ROs ,2SROs Restorewithin2hours
B.2ROs ,1SRO Restorewithin1hour
C2ROs, 1 SRO R estore w ithin2hours D.2ROs,2 SROs Restorewithin1hour
66 of 100
WattsBar Nuclear Plant2008InitialLicense
Written Exam SENIOR REACTOR OPERATOR Question Number: 67WiththeSteam
DumpModesw itch intheT avg mode , what determines
whethe r th e lo ad rejection controllerortheR x trip controller
will be inserv ice?A.L ossof Load(C-7)Interlock.B.LO-LOTavgInterlo
ck (550°F).C" A" T r a i n R eac t o r Tri p b reakerpos i tion.D."B"Train Reactor T rip breaker position.67 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR QuestionNumber:68 Giventh e followingplantconditions:*Uniti s inMode 6.*15fuel assemblieshavebeenreloade
d after a complete core off-load.*Sourc eRangeN-13 1 indicates10cpsandis
selecte dforaud ible count rate indication.
- SourceRangeN-132indicates5cps.
I n ac cordancewithFHI-7,"Fu el Handling and Movement" ,whichONEofthefollow
ing unanticipated
changes in count rate requires suspensio nofcore alterations?
AN131indica tes25cpsand N 132 ind ica tes8cps.B.N131indicates 15cpsandN13
2 ind icat es20cps.C.N131indicates 40cpsandN132
indicates8cps.
D.N1 31 indicates20cpsandN132indicates15cps.68of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 69APow er Range chann elhasfa iled requiringthecrewto implement AOI-4, NIS Malfunctions.Th eUShas enteredtheappropriateTechnicalSpecifications and statesthata fluxmapw ill be requir ed per Surveillance
Requiremen
t 3.2.4.2.SR 3.2.4.2d irects the operato rstoverifyOPTR
iswithinl imitsusingmoveableincoredetectors o nce within1 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> andevery 1 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thereafter.Whatisthemaximumtimefor th e initialperformance of th e flux mapandthemaximum tim e f or sub sequent performances?
A.B.c.D.Initial Performance
1 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s15hours 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s15ho urs Subsequent
Performances
1 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s12hours15hours15hours69of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 70 Giventhefollowing conditions:*Un it 1 shutdownis i n progress.*R eactor power is14%andde creasing.*Int ermediate Range NI-36 fails HIGH.Which ONE ofth e following identifies how thefailure ofth e NIwi ll affect th e reactor tripsy stem andthe effectthefa ilure w ill haveonthe Source Rang e Nls?Reactor Trip System A.Reactortripwillo ccuratth e time of failure.B.Reactor tripwilloccuratth etimeof failure.C.Reactortripwill occur if power reduction is continued.DReactor tr ipwillo ccur i f power reduction iscontinued.Effect on Source Range Nls Source Ran ge Nls will havetobe MANUALLY reinstated.
Source Range Nls will AUTOMATICALLY
reinstate.Source Range Nlswillhave t o b e MANUALLY reinstated.So urce Range Nls will AUTOMATICALLY
reinst ate.70 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 71 An individ ual enters a RadiologicalControlledArea(RCA)c over ed b y a Gener al RWP to perfo rm equipment inspect ions.Which ONE of the following identifiesanarea w ithin the RCA wh ere a Job Sp ecifi c RWP is requiredbefore ent ryisal lowe d , i n accordance
withRCI-153 , R a diati on Work Permits?A.Ar ea where whole b ody dos e ratesexceeds100mrem/hr.B.Are a post edasHotParti
cle Area.C.Areawithgeneral contaminationlevels greater than200dprn/f Oucrn".D.Area where total e xpected dose is greater than 5 mrem.7 1 o f 1 00
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR QuestionNumber:72 Giventhefollowingplantconditions:*Followinganaccident,bothTrai nsofCont rol Room Isolationhavebeen initiated.*Several Au xil iary Buildin gAreaRadiation M onitors r isetothealarmsetpoint.W hic h ONEo fthefol lowingMCRai r inta ke radiation monitorsw ill detectandalertthecrewofa
rad iation hazardenteringthecontrolroomandwhat
actions willtheARI direct the crewto perform?A.O-RM-90-125
, B.O-RM-90-125, C.O-RM-90-205,D.O-RM-90-205,StopMCR Emergency Pressurization
Fans.Al ign Emergency PressurizationFansuct ion to alternatesourc
e.StopMCR Emergency Pressurization F ans.Align Emergency Pressur ization Fan suction to alternate source.72 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 73TheOp er ator-at-the-Controls(OAC)is respondin gtoan accident.Herec ognizesthathemust
t a ke actions which areNOTcontainedinthe emergency operating procedure in effec t and are NOT coveredb y prud ent oper ator a ctions.Wh ichONEofthe following descr ibesthep roperactiontobe
taken?A.TheOACshalltakenoactionuntila
procedure is developedorrevised.
B.TheOACshallobtain
approvalfromalicens
edSROpriortotakingaction
.C.TheOACshouldobtain
concurrence
from another licensedROpriortot
aking action.D.TheOAC should immediately
take appropriate
actions necessary and informtheSROwhen
t ime permits.73 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 74 Gi ven th e following:*ASiteArea
Emergency (SAE)hasbe en declaredonUnit 1.*Tw o hours aftertheSAE declaration
, an indiv idualistobe authoriz edtoreceive an Em ergen cy E xposure radiation dose above the TVA who le body dose lim it during the mitigationofthe emer genc y situation.In accordancewithEPIP-15 , Emergency Exposure Guidelines , whose approval isrequired for the individualtorece
ive the dose?A.TSC Radcon Manager.B.Onshift Sh ift Manage r.C.Sit e Em ergency D irector.D.SiteV ice Pr esident.74of100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Quest ion Number: 75 Whi chONEofth e followingidentifieswhereaPortable
Satellite Telephone , availableforuse du r inganemergency , isloc ated?A.M ainControlR oom B.Technical Support Cen ter C.Jo int Information C enter D.Operations Support Center75of100
AOI-30.2 WBNFIRESAFE SHUTDOWN Rev.27 Paq e 17 of 129 1 4.5SafeShutdownLogicDiag
ram NOTE S (1)INITIATINGE VENT I SANAPPENDIX R FIRE(2)REFERT O SECTION 4.3 FOR A CO MPLETE DESCRIPTION
OF THE SHUTDOWN KEYS , THEIR FUNCTIONS AND COMPONENTS.(3)LEGEND FOR DIAGRAMSYMBOLSASFOLLOWS'DESCRIPTION O F K E Y KEY NUMBER I<SAFETY FUNCTlONORE.ND STATE TO BE AnAINED (4)OFFSITEP OWER NOT CR EDITED FORALTERNATIVESHUTDOWN.(5)R CP THERMAL B ARR IERCOOLINGREQ UIRES SUPPOR T OF ERCW(KEY1 C)&CCS(KEY 1B).,........:::::l i.J i.J:J!\J()'6!{\j C;I V (t\<t:\
Final Submittal(BluePaper)FINALSRO WRITTEN EXAMINATION
AND REFERENCES
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 76 Given the following conditions
- Unit1isat100%
power.Solid State Protection
System (SSPS)Train'B'Actuation Logic testingisbeing performedusing1-SI-99-1
OB with:*Tra in'B'SSPS Mode Se lectorswitchinthe
'TEST'position.*Train'B'SSPSI nput Err or Inhibitswit chinthe"INHIBIT"pos
ition.Aun it trip occursduetothelossofoneofthetwo48vDC
power supplies on TRAIN'A'SSPS.The following"First Out" annunciatorsarelit: 1-XA-55-4C.
Turbine Trip First W indow73C-"R X TRIPBKRSRTA&BYA
OPEN" Window74C-"RX TRIP BKRSRTB&BYB OPEN" Window74B-"MFPT A&B TRIPPED" 1-XA-55-4D
Reactor Trip First Out Window 76B"TURBINE TRIP" WhichONEofthefoll
owing id entifiesboththe sequence of eventsofthe unit trip,andthetim e all owed to make the requiredNRC50.72 notification
?Sequence of Events A.Turbine trip caused the Reactor trip.B.Turbine trip caused the Reactor trip.C.Reactor tr ip caused the Turbine trip.D.R eactor trip causedtheTu rbine t rip.NRC Notification
Required Within Four Hours Eight Hours Four Hours Eight Hours 76 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 77 Given the following plant conditions
- Core burnupis1200 MWO/MTU.*Indicated reactor power is stable at 100%.*VCTlowlevel alarm annunciates.
- Auto makeuphasfailed.*Actual VCTlevelhad loweredto5%before the crew completed the appropriate
corrective
action.*Reactor power has stabilized
at approximately
97%power.Ifthis event had occurredwithcore burnup at 16600 MWO/MTU, the magnitudeofthe change in reactor power wouldbe(1),andthe SignificanceLevelofthe
Reactivity
Management
Event classification
would be recordedonthePER (Problem Evaluation
Report)by(2)_(1)(2)A.less Reactor Engineering.
B.greater Reactor Engineering.
C.less the Management
Review Committee.D.greater the Management
Review Committee.77of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 78 Given th e following:*Unit1 isinMode5fol lowingar efueling outage.*RHRpump1A-Aisinservice.*T he operating crew i s drawing vacuumontheReacto
r Coo lant System.*Th eRHRpumpbegins toshowsignsof
cavitation.
Which ONEofthe following identifies bothho wtheRHRpump
motor ampsa re affected wh enthepumpis cavitating
,andthe mitigating
strategythatw ill be implementedifthe cavitation
cann ot be terminated
?Motor Amps A.Unstabl e and fluctuat ing.B.Unstable andfluctuating.C.Stable but reduced.D.Stablebutreduced.
Mitigating
Strategy Break vacuumperGO-10, Reactor Coolant S ystemDrainandFill
Operations, then enter AOI-14,Lossof RHR Shutdown Cooling.Immed iately enter AOI-14,LossofRHR Shutdown Cooling.Break vacuumasd irectedbytheAOI.BreakvacuumperGO-10,Rea ctor Cool ant SystemDrainandFill
Operations
, then enter AOI-14,Lossof RHR Shutdown Cooling.Immediately
ente r AOI-14,LossofRHRS
hutdown Cooling.Brea k vacuumasd irected b y th e AO I.78 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 79 Giventh e followingconditions:*Thepl ant is operatingat100
%power ste ady state condit ions.*Allsystemsare aligned normally.*Afailureofth e Pr essurizer Spra y Valve PCV-68-340D causesittogo fullOPEN.*TheOACha s attempte dtotake manual controloftheSpra y Val ve,buti s unablet o close i t.*Pressurizer pressure continuestoLOWER.
Wh atist he appropri a t e mitigation strategya nd whichpro cedure(s)will beus edtoimplement th e strategy?A.EnterAOI-18 , M a lfunctionofPressurizer Pr essure Control System , initiate a Reactor Trip,tripRCP#1 , then enter E-O, Reactor Tr ip or Safety Inject ion.B.Referto ARI-90-B ,PZRPRESSLODEVN
BACKUPHTRSON, isolat eTrainBEssenti
al AirtoConta inmenttofa il th e Pressurizer Spr ay Valve closed,andthenent
er AOI-1 8.C.Refer t o ARI 90-B , PZR PRESS LO-DEVN BACKUPHTRSON,isolateTrainAEssential Air to Containmentt
ofailthePr essurizer Spr ay Valve closed,andth en enter AOI-1 8.D.Enter AOI-18, Malfunction
of Pressurizer
Pressure a Reactor TripANDSI , tri pRCP#1 , th en enter E-O, Re actorTripor Safety Inject ion.79of100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 80 Giventh e following:*The plant i s operat ingat100%power.*Th e125VDC VITAL CHGRIIIfailsandits
output brea ker opens.*A report i s receivedthatther eisarc ing occurringonVital Battery III.*Th e Sh ift Manag er directsthat0-B KR-236-3/1 09 125V V ital Battery III Breake r, betwe en Vital BatteryIIIandVitalBatt
ery Boa rdIIIbeopened.*Th e Un it Supervisor
has determ ined that powertoVital Battery BoardIIIw ill berestored usingVital Battery V,i n conjunct ionwiththe Spare Batter y Charger.*Vital Battery V i s currentl y in serviceto Battery Boa rd V.WhichONEofth
e following describesthee xpect ed indication
on 1-EI-57-94, Vita lBattBDIII AMPS wh ich w ill confirm that powerhasbeen restored to Battery Board III , AND what isth e operability
statusofV ital Battery Board III?1-EI-57-94 (SattSOIII Amps)Indication
A.Indicating UPSCALE from zero.B.Indicating DOWNSCALE fromze ro.C.Indicating
UPSCALEfromzero.D.Ind icating DOWNSCALE from zero.80of100 Operability
Status of Vital Satt.SOIII Can NOT be considered operable w ith b oth V ital Batter yVa nd thesparecharger connected concurrently.Can NOT be cons idered operable withbothVital BatteryVandthe spare charg er connec ted concurrently
.Operablewiththe spare chargerandVital Battery V connect edtothe Battery Board andwithallapplicable surveillances
on V ital Battery V satisfied.Operablewiththe spare chargerandVital Battery V connectedtothe Battery Boardandw ith all applicable
surveillances
on Vital Battery V satisfied.
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 81Withthe plantatfull power , and during the Shift Turnoverforthe 1900 shift ,theUnit Supervisor
is inform ed o f t he follow ing:*1-LS-63-50A (RWST Low Level)was declared inoperable
at 1000thatday.*Itwasplacedinthe
configuration
required by Technical Specificationsat1400 ,andis e xpectedtorema in inoperable
until 2300.*Arequ ired surveillance
instruction
on 1-LS-63-51A (RWST Low Level)must be completed by 2330 today to prevent beingoutof frequencydueto exceed ingtheNRClatedate.*The surveillance
involves having 1-LS-63-51Ainthe required configurationfor2 hours.Ifthesurv e illance i s completedb y 2330,whichONEofthe follow ing describe sthee xpected effectonthe automatic sw itchover to containment
sump function while 1X6 3-51Aisoutof.? service......A.Functional.Even thoughtwolevel switches are TRIPPEDandare inoperable , the remaining operable level switches are sufficient
for switchovertobe functional.
B.Functional.
Even thoughtwolevelsw
itches are BYPASSED, the remaining level switches are sufficientforsw
it chovertobe functional.
C.Notfun ctional , becausetwolevelswit
ches are TRIPPEDandat least thre e level switches are required for switch overtobe functional.
D.Not functional, becausetwolevel switches are BYPASSED ,andat least three level switches are required for switchovertobe funct ional.81of100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 82 Gi ven the follow ing:*Theu nitisa t 100%powe r a nd a ll equipmentis
available.*AplannedCaskDecontamination
Co llector Tan k (CDCT)rel ease is inpro gress when the following occurs:*Annunciator
181-A"WDS RELEASE LINE 0-RM-90-122
L1QRADHI" a larms.*The MonitorTankle velis70%and lowerin g.WhichONEofthe
following id entifies wheth ertherelea se permit was violatedandthereleas
e p ermit r equirements to allow theCD CT relea s e tocontinue, i n accordance withS OI-77.01,LiquidWasteDisposal?Permit Violated Release of CDCTThesame release perm itcanbeused follow ing independent
verif ication of correctvalvel ineup.Anewr eleasepermitmu st be gener ated.IThere lease perm itwouldbe v iolated bec ausetheliquid releas edwasnotsampled
.priortotherelease
.Th e release permitwouldbe!violatedbecau
setheliquid i rel easedwasnotsampled A.i I priortotherelease., Th e release permitwasNOT C.v iolated because the releaseThesame release permitcanbeused was terminatedbythehigh following independent
ver ification of r ad signa l.correctvalvelineup
.The releasepermitwasNOT
, D.violated becausethereleas eAnew releaseperm
it mu st be generated.,.w a s terminated by th e hig h I I rad signal.I i I l B.82of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 83 Giv enthefollowing plant conditions:*Unit1 w asat100%pow erwhenaMainControl Room (MCR)evacuationwasrequired.*Thec rew enteredAOI-27 , Ma in Cont rolRoomIna ccessibility.*Thecrew performed ES-0.1, Reactor Tr ip Response, priortoleav ingtheMCR.*While performingactions fromth eACRa SafetyInjection occurs.WhichONEofth e followingwillbeth estatusofthe
MSIVswhenthe crew establishes
control fr omtheAu xControlRoomand
describes the correct proced ure usage?A.B.C.D.MSIV Status Op en Op en C losed Clo sed Procedure Usage AOI-27willbethecontroll
ing procedure because itiswrittenwith
mitigatingactionstorespondtoa
Safet y Inject ion.E-O, Reactor Tr iporSafety Inj ection, would beus ed because AOI-27iswritten assuming no other accident isoccurring.AOI-27 wi ll be th e controll ing p rocedur e b ecause itiswritten with mit igating actions to respondtoa Safety Injec tion.E-O , Rea ctorTripor Safety Injection ,wouldbeused
because AOI-27iswrittenassumingno other accident i s occurring.83of100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 84 Given the following:*Thecr ew is perform ing FR-H.2 , Steam Generator Overpressure,foran overpre ssur e conditiononSG#2.*Wh en thestepisaddressedtocheck affectedSGsNRleveli t is noted th at theS G#2levelis indicating
94%narrow range.WhichONE ofth e following id entifies the correct crewact ionsasa resultoftheSG level mor catm q 9 4%?A.Cont inueinFR-H.2, b utdonot initiatean y steam release unt il TSC evaluation
is complete.B.ContinueinFR-H.2 , steam release may continueuntilNRlevel
indicates 100%.C TransitiontoFR-H.3, Steam Generator H ighLevel,butdonot
initiate any ste am release until TSC evaluation
is complete.D.Transition t o FR-H.3, St eam G ener atorHighLevel, steam release m ay c ontinu e unt il NR level indic ates100%.8 4 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR QuestionNumber:85Giventhefollow
ing:*Unit1experiencedaReacto r Tr ip an d Saf ety Inject ion.*Thecr ew transitionedtoFR-Z.1,HighConta inment Pressure,fromE-1 , Los s of ReactororSecondary Cool ant.*Whil eFR-Z.1wasb
eing performed ,thecrew transitionedtoFR-P.1, Pressurized Thermal Shoc k.*TheSTAre portstheconta inm ent pre ssure ha s dr oppedandthecontainment statu streeisGREENandthatnootherREDo
r ORANGEpathsexist.WhichONEofthefollow
ing identifies th e b asis oft he FR-P.1stepfor checkingRCSpressure gr eaterthan150ps ig,andtheprocedure the creww ill implementifatransitionism ade from FR-P.1 duringperf ormanceofthest ep?A.Toprecludetheneedto perform FR-P.1 actions , s ince pressurized thermalshocki s not a seriousconcern
fora large-b reak LOCA;TransitionismadebacktoE-1.B.To precludetheneedto perform FR-P.1 actions , since pressurizedthermalshockisnota
seriousconcernforalarge-break LOCA;Transit ionismadebacktoFR-Z
.1.C.T o avoid delays cause dbyunne cessarysoakperiodsrequ
iredbyFR-P.1.Transitionismadeba cktoE-1.D.Toa void dela yscausedby unnecessarysoakperiodsrequiredbyFR-P.1.TransitionismadebacktoFR-Z.1
.85of100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 86 Given th e following:*Unit 1wasi n Mode2withs tartup i n progresswhenalossofoff-site pow er o ccurred.*The decision was madetop lace the plant inMode5.*The crew implement ed ES-O.2, Natural Circulation
Cooldown , and started cool ing the pl ant d own.*Four(4)hours afterthec ooldownwasin itiated both trains of offsite powerwererestored to the plant.*The crew d etermines all criteria to restart the RCPsaremete xceptforthe#1seal
leakoffflowonRCP#2which islowerthan the normal operating band.Whi chONEofthe following identifiesa change that caus es an increaseinthe#2RCPseal
leakoff flowandtheact ions t o b e ta kenandpro ceduretobe used iftheseallea
koff flow cannot beestablishedw
ithin the normal operating band?A.Lower PRT pressure;StartRCP#1, cont inue performing
ES-O.2untilallRCS
temperatu res a relessthan 200°F, th en transitiontoGO-6 , Un it Shutd ownFromHot StandbyToCol d Shutdown.B.LowerPRTpressure;Starttheother 3 RCPs an d i mmediately transitionfromES-O.2toGO-6, Unit Shut downFromH ot St andbyToCold Shutdown.C.Lower VCT pressure;StartRCP#1 , continue perform ingES-O.2untilallRCS
temperaturesarelessthan200
°F,thentr ansit ion to GO-6 , Unit ShutdownFromHot StandbyToCold Shutdown.D.Lower VCT p ressure;Start t he other3 RCPs andimmediately transition from ES-O.2toGO-6, Un it ShutdownFromHotSt andbyToCold Shutdown.86of100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR QuestionNumber:87Giventhe following:*Unit1isat
100%power.*1-SI-99-10-B,31Day FunctionalTestofSSPSTrainBand
Reactor Trip Breaker B , isin progress with ReactorTripbypass
breaker(BYB)closed.
- Appendi x F , Reactor Breaker Replacement.of1-SI-99-1
O-Bisin progress w ith Rea ctor Tr ip BreakerB(RTB)rac ked out.*A feedwater transient occursduetoan electr ical power loss , resultingintheMCR operator MANUALLY trippingthereactor.WhenTavg , Pressurizer
Pressure,andSGleve lsarestabi lizedposttrip , the following conditionsar
e observed:*All4Diesel
GeneratorsrunningbutNOT
connectedtothe shutdown boards.*All Reactor Tr ip Breaker and Reactor Trip Bypass breaker ind icatinglightson1-M
-4 are DARK exceptforthe GREENlightonthe
Reactor Trip Bypass BreakerB(BYB)whichis
LIT.WhichONEofthe
following identifiesboththe position of Reactor Trip BreakerA(RTA)andthe
correct SRO decisionrelativeto
completing
1-SI-99-10-B
following the stabilizationoftheplantandthe electrical
power restoration?
A.B.C.D.RTA Position Closed Closed Tripped Tripped 1-51-99-10
-8 Status The surveillanceisrequiredtobe
completed.Thesurve illanceisNOT requiredtobe completedwiththeplantinthisMode
.The surveillance
is requiredtobe completed.The surveillanceisNOT requiredtobe completedwiththeplant
inthis Mode.87 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 88 Giventhe following:*Followinga reactor tr ip the plant e xper iencedatotallossoffeedwater.*The condition causedth e cr ew to initiateRCSble
edandfeed.*SUbsequentlythe
TDAFW pump w as restor ed to serv iceandthe crewisr eady to est ablish AFW flowtothe selected ste am generator.*Other plantconditionsinclude: o SelectedSGWide Range leveli s 4%.oRCSloophotleg
temperature
a t 558°F.o Core exit thermocouple
temperatures
a re RISING.Inaccordancew ith FR-H.1, LossofSe condary Heat Sin k , fe edwater flowwillbere-e stablishedtothesele ctedSGat...A.them inimum detectable
flow gpm.B.less than 10 0 gpm unti lWRlevel>15%.C.arate that causes wide range leve ltoriseandRCShot
legto drop.D.a maximum rate.88 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 89 Giventh e followingconditions:*Th e pl ant is shutdownInMode4 witha ll safetyrelated
equipm ent operable.*Duringtheperformance
of surveillance
0-SI-215-21-A, DIESEL GENERATOR 1A-A BATTERY QUARTERLY INSPECT ION,i t isreportedthattheFloatVoltagevaluesf
or three(3)connectedcellsa
reasfollows:Cell17=2.09v Cell 3 4=2.06 vCell39=2.12v*ALLothe r conn ected cells haveFloatVoltage values greaterthan
2.13v.*AL L other parameters
m easuredduringtheabo
ve surve illancearenorm al.WhichONEofthe
following describesthestatusofDG1A-A
batteryANDoftheDG1A-A?
REFERENCE PROVIDED Status of Battery A.B attery is degrad edbutitcanbeconsideredoperable for 31days.B.Batteryi s degradedbutitca nbecons idered operablefor31days.
C.Batteryisinoperable.D.Batteryi s inoperable.Status ofDG1 A-ANOTe ch Specortracking only entry requir ed f or DG.TechSpec tracking on ly en try requiredforDG.DGis inoperableandTechSpec
trackingonl y entryisrequired
.DGis inoperableandTechSpecentr
yisrequ ired.89 of 100
WattsBar Nuclear Plant2008InitialLicense
Written Exam SENIOR REACTOR OPERATOR Question Number: 90 Given the following conditions:*Unit1is operat ingat100%power.*ERCW strainer 28-8 plugs.*Itis determinedthatthe strainermustbe isolated.WhichONEofthe
following identifiestheactiondirec
ted by AOI-13 ,Lossof Essential Raw Cooling Water , to mitigate the isolationofthe28 strainerandthePSArisk
statustheplantwillbeinduetothe
strainer iso lation?AOI-13 actions A.Realigncool
ing watertotheAtraind
iesel generators
.8.Crosstiethe28heade
rwiththe1A header unt il strainer is repaired.C.Realign cooling watertotheAtraindiesel
generators.
PSA risk Orange O range Red D.Crosstiethe28 headerwiththe1A header until strainerisrepaired
.R ed 90 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 91Giventhe following plant condit ions:*Duringa startup ,theplantisinMode4
.*GO-1, AppendixC,Mode 4-to-Mode 3 Review and Approval,hasbeen completeduptothelaststep
, Operations
SuperintendentHoldPoint , for granting approval to enter Mode 3.*During scaffoldingremovalactivities , a worker contactstheairlineto
1-FCV-62-93 , Ch argingFlowControlValve,resultinginpullingtheairlineloosefromtheval
ve operator,suchthattheairsystem
remains intact ,duetocrimp
ingofthelineontheair
supplysideofthebreak
.Whi ch procedures
w illtheUnit Supervisorusetorespondtothis
eventandthebasisfortakingquickactiontolimitthe
effects?A.TheUnit SupervisorwilluseAOI-10
,Lossof ControlAirtod irect actions to prevent Pressu r izer le vel fromexcee d i ng 92%ino rder tomaintain the presence o f a steambubbleinthe
pressur izer.B.TheUn it SupervisorwilluseAO I-10,Lossof ControlAir,andd irect actions to prevent the level decreasetolessthan17
%to ensure subcooling
margincanbe maintained.
C.TheUnitSup
ervisorwilluse SOI-62.01, CVCS-Charging
and Letdown and direct actions to preventthelevel decreasetolessthan17
%to ensure subcooling
margincanbe maintained.
D.T he Unit Super visor willu se SOI-62.01, CVCS-Charging and Letdown , to directactionsto prevent Pressurizerlevelfrome
xceeding 92%in order to maintain the presenceofa steam bubbleinthe pressurizer
.91 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 92 Given the following:*Unit1wa s operating in Mode1at14%reacto r power.*Alossof condenser vacuum occurs result inginan automatic turbine trip.*The operatingcr
ew stabili zes th e plant.WhichONE ofth e f ollowing identifies b othhowth e condenser circulating
water box t:.T s wi ll b e affected and thenotificationsrequired du e t otheturbine tr ip in accordancew
ith SPP-3.5, Regulatory
Reporting Requirements?
Water Box t:.T Notifications
requiredA.Rises Internal TVA not if ications only B.RisesNRCand Internal TVA notifications
C Lowers Internal TVA notif ications only D.LowersNRCand Internal TVA notificat ions 92 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 93 Giventh e following:*At0100*At0200*At1 100*At1200Unit1 entered Mode3duringshutdownforare
fu eling outage.AOI-7.01, Maximum Probable Flood , was implemented
duetoe xtremely h eavy rainfallinthe upstream watershed.The plant i s i n Mode4onRHRwith
cooldown i n progress withtheRCS pressure320ps ig and temperatu re 22 0 0 F.River System Op erations(RSO)confirmsth efloodlevel a t the plant i s predictedtoc restatEI.7 30'within the next 3 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.WhichONEofth
e following identifies
boththeFlood Stage Pr eparation level (s)thati s/are r equiredtob e completed.a nd howthecoolingofthecore willbe maint a inedi n accordancewith AOI-7 after the preparations
are complete?A.Onlyth e proc edure for Stage 1 Preparationsi s requiredtobe completed.Core cooling will be mainta i nedbythe steam generators
w ith water be ing suppliedbyhigh pressure fire protect ion w iththeRHR system removed from serv ice.B.Onlythe procedure for Stage 1 Preparat ions is requiredtobe completed.Core cooling w ill be maintain edbythe SpentFuelP ool cooling syst em cros s t iedwiththeRHRs ystem.C.Both Stage1and Stage 1/Preparat ions procedu res are requiredtobe completed.
Core coolingwillbe mainta inedbythe steam generators
with water being supplied by high pr essure fire protect ionwiththeRHR
system removed from serv ice.D.B oth St age1andSt age II Preparat ions procedures
are requiredtobe completed.Corecoo ling w ill be maintainedbythe SpentFuelPoolcool
ing system crosstiedwiththe
RHR system.9 3 of 100
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR QuestionNumber:94 WhichONE ofth e f ollow ing satisfiestherequirementofFHI-7forthemaximum numberoffu el assembliesallowedoutside o f approved storage?A.Two unirradiat
ed assemblies w ithin the fuel-handling
area.B.Twoirradiated assemblieswithinthespentfuelstoragepool
boundary.C.On e assemblyinthetransfer c art ,twoa ssembliesintheRCCAfixtureandon e assemblyi ntherefuel ing machine mas toverits properlocationinthe
reactor vessel.D.On e assemblyinthe transfer cart , two assembliesintheRCCAfixtureandoneassemblyi n th e refueling machinemasto verthere actor sideupender.94 of 100
Watts Bar Nuclear Plant 2008 Initial License Written Exam SENIOR REACTOR OPERATOR Question Number: 95Withth e pl antatfullpower,theChem
istryLabhas just informedtheUn
it Superv isorthatth eRCSchloridelev el i s 1650ppbandthattheSGchlo
ride leveli s 200 ppb.Thesourceofan y impurity ingresshasNOTyetbeen
identified.Basedonthe reported values, (1)whatisthe MOST restrictiveActionLevelthatmustbe
entered a nd (2)theimpactonplantoperationscausedbytheA ction Levelen try?ill A.ActionLevel 3 forRCS chloride le velB.A ction Level 3forSG chlor ide level C.Action Level 2forRCS Chloride level D.A ction Level 2forSG Chloride level Init iate actionstota ke the reacto r sub-criticalasquickly as practicable
ina controlled
manner and reduceRCStemp erature to<250*F.Initiate actionstotakethe reactor sub-critical as quickly as practicable
ina controlled mann erandreduc eRCStemperaturet
o<250*F.Restore parameter to belowActionLev el 1 within 24hoursor reduce reactor powertolessthan5%.Restore param eter t o below Act ion Le vel 1 within 2 4hoursor reduce reactor pow ertoless t han 5%.95 of 10 0
WattsBar Nuclear Plant2008InitialLicense
Written Exam SENIOR REACTOR OPERATOR QuestionNumber:96 Giventh e f ollowing*Un it1at100%power.*Diesel Generator(DG)2A-Aistoberemovedfrom
servicefora maintena nce out agewithaplannedoutofserviceof102hours
.Which ONE ofthe followingidentifies Unit1equipmentthatislist
edinTechSpec
3.8.1 , AC Sources Operating,BasesCont ingency Actions ,asequ ipment that istoremaininservic
e concurrentl
yduringtheDG2A-Aoutagema
i ntenance t obeincompl iance w iththeTechSpec?A.ReactortripbreakerA(RTA).B.TDAFW pump.C.RHRPump1B-B
.D.AnyS/GAFWlevelcontrolvalve
.96 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 97 Which ON Eofthe following identifiesBOTHthe minimum decay time requiredtoallow the conten ts o faGas Decaytankto decay prio rtorelease and who can waive the minimumtimein accordance
with SOI-77.02, Waste Gas Disposal system?DecayTime RequiredWhoCan WaiveA.60 days C hemis try DutyManager B.6 0 days Radiation Protection Manager C.8d ays Chemistry DutyMa n ager D.8 days Radiation Protection Manager 9 7 of 100
WattsBar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 98 Giventhe follow ing plant condit ions:*Un it 1 i s i n Mode4with preparat ions be ing made fo r fuel moves.*As parto f p erforming the Channel Operat ional Test (COT)for 0-RM-90-1 0 2, Sp ent Fu elPoolPitArea
Monitor, a source check istobe performed.
What isth e effec t of performingth
e source check portionof this test , a nd whatisthe SRO's r esponsibilityforTech Spec/LCO Tracking Sheet entry?A.Thisw ill resultinan automatic actuationofTrainAof ABGTS.The SROwillmakea n entryontheLCOTracking Shee tthatTra inAof ABGTS i s inoperable.
B.RM-90-102 outputwillbeb locked during the source check, the SRO will make an entry ontheLCOTracking SheetthatTra inAof ABGTS is inoperable
.C.RM-90-102outputw illbeblocked during th e source check ,theSROwillmakeanentryo ntheLCO Tracking SheetthatRM-90-102is
inoperable.D.Thisw ill resultinana utomatic actuat ionofTrainAof
ABGTS.The SRO w ill make an entryontheLCO Track ing She et that RM-90-102is inoperable.98of100
Watts Bar Nuclear Plant2008Initial
License Written Exam SENIOR REACTOR OPERATOR Question Number: 99 Giventhefollow ing:*Unit1e xperiences
a Safety Inject ionduetoasteam
generator t ube ruptu re o n SG#1.*AllR eactor Coolant Pum pswereremov ed from serviceduetolossof
support s ystems.*RCScooldown at maximum r ate t otargetincore
temperatureisin progress.*TheSTAreportsthataREDpathforFR-P
.1 , P r essurized ThermalShock,exists onRCSLoop1ontheFR-O,StatusTr ees.WhichONEofthefo
llowing identifieswhenthetransitiontoFR-P.1shouldbemade?
A.Immediately t rans itiontoFR-P.1fromE-3becauseFR-P
.1 prov ides act ionstolim it cooldownand
repressu rization o ftheRCS.B.RemaininE-3 unt il the cooldown i s completeandthent ransitiontoFR-P.1onlyiftheREDpathsti ll exists becausethecooldownisneeded
toallow depressur izationoftheRCS.C.Remain inE-3 until the cooldown i s completeandthen transitiontoFR-P.1 ev eniftheRED p ath n o longer exi sts be cause thecooldowni s needed to allowd epressurizationoftheRCS.D.RemaininE-3 unt ilthesafetyinjection
i s terminated,thentransitiontoFR-P.1 only iftheREDpathstillexistsbecauseFR-P
.1providesact
ionstolimit cooldown and repressurizati
onofth e RCS.99 of 10 0
WattsBar Nuclear Plant2008Initial
LicenseWrittenExam
SENIOR REACTOR OPERATOR Question Number: 100 G iven the following conditio ns:*Theplantisatfull
power.*Areport was receivedofa tornadobe ing sightedovertheWa ttsBarTraining Center, movingi n a northwest direction.Th e tornadocontinuedtomoveacrossHi ghway 6 8 an d then dissipated
without touching down onsite.*TheMCRcr ew has just enter ed AOI-8, TornadoWatchor Warning.*C onfirmation
was received th atnovis ible dam agehadbeenrec
eivedtoanystructures or equipmentonsite.*TheSh ift Manager evaluatestheRad
iological Emerg encyPlan(REP)anddetermines the conditionsforanNOUEwere
initiallymetbutarenowfully
resolved.Whi chONEofthe following identifiestheODSandNRC
notif ication requirements
in accordancewiththeREP
?A.B.C.D.ODS notification
Reportbutnot declaretheevent.R eportbutnot declaretheevent.Declare and terminate the event atthesameclocktime.
Declareandt erminate the ev entatthesamecloc
k tim e.NRC Notification
required within:15minut es.1hour.15 minutes.1hour.100of100
Battery Ce ll Paramet ers 3.8.6 3.8 ELECTRI CAL POWER SYSTEMS 3.8.6 Battery Cell Parameters
LCO 3.8.6 APPLICABILITY
- A CTI ONS Battery c el l parameters
f or 1 25 V vital ba tteries an d 125 V diesel g ener at o r (DG)batteries shall b e within the lim its of Table 3.8.6-1.When associated
DC electrical
p ower su bsystems and DGs are required to be OPERABLE.-------------------------------------N OTE-------------------------------------Separate Conditi on entry is all owed for each battery bank.A.CONDITION One or more batt e ries with one orm ore battery ce ll parameters
n ot within Categ ory A or B limits.A.I AND A.2 AND A.3 REQ UIRED ACTION Ve r ify pilo t cells e lectro lyte level and f loa t voltage meet Table 3.8.6-1 CategoryC limits.Verif y batter y cel l parameters
meet T a ble 3.8.6-1 Category C limits.Restore battery cell parame ters t o CategoryA and B limits o f Table 3.8.6-1.COMPLETION T IME 1 h our 24h ours AND Once per 7 days th ereaft e r 31 days (c ontinu ed)WattsBar-Unit1 3.8-33
A CT I ONS (contin ued)COND ITION RE QUIRED ACTION BatteryCellP aram et e rs 3.8.6 COMPLETIONTIME
B.Re q ui redA cti o n and a ss o ci ated C omple t i o n Tim e o f Conditi o n A no t m et.OR One ormore batteries with av erage ele ctr ol yt e t emp erat ure o f the repr esentati ve cells<60°Ff or v it al b a tteries and<5 0°F f o r DG batt eries.O R One o r more bat teries wit h one or m ore ba t tery ce ll param et ers no t wit hi n Categ oryCval ues.B.1 D e clar e asso ci at e d batt ery i n op era b le.I mmedi a tely S U RVEILL A N C E REQU IREMENTS SURVEILLA NC E FREQUE NC YSR3.8.6.1 W a tts B a r-Unit 1 V erif y batter y cel l parametersmeet Table 3.8.6-1 C a te g o ry A lim it s.3.8-3 4 7 da ys (co ntin u e d)
SURV E ILLA NC E REQUIREMENTS(c ontinued)SURVEILLANCE B att eryCellParam et er s 3.8.6 FREQUEN CYSR3.8.6.2SR3.8.6.3 Wa tts B ar-Un it1 Veri fy batt erycell p aramet ers m eet Table 3.8.6-1 Categ or yBl imits.Veri fy a verage el e ctr ol ytetemperature
o f repres entativecel ls is60°Ff or v ital batt eries and50°F f or the DG batter ie s.3.8-35 92 days AND O n cewi thin 24h ours after a ba t tery disc harge<11 0 V f or vital batterie s (113.5 V for vital battery Vi or1 0 6.5V f or DG batt eries AND Once within 24 h ours a f ter a batter y ov e rc harge>150 V f or vital batt eries (155V for v ital batteryV)o r 145V f or D G b att e ries92d a ys
BatteryC ell Parame ters 3.8.6 Table3.8.6-1(p age1o f 1)Battery Cell Parameters
Requi rements CATEGORYA: CATEG ORY B: CATEG ORYC: PARAMETER LIMITS F OR EA CH LIMITS F O R E A CH AL L OWABLE L IMIT DESI GNATED PIL OT C ONNECTEDCELLF OR EACH CELL CO NNECTED C ELL El ectrolyte L eve l>Min imum le vel>Min imum l e vel A bo ve t op o f in dicati on mark, indi cati on mark, plat e s, andn ot and s: 1/4 inch and s: 1/4 inch over flowing ab ove maximuma bov e maxi mum l e vel indicati on l evel in d ic ati on mark (a)m a rk (a)Fl oat Voltage2.13 V2.13 V>2.07 V Speci ficGr avity1.2001.195 Not m ore than (b)(c)0.020 bel o w AND a ve rage of all--c on nected c ell s A verag e o f all conn ected cells AND-->1.205 Aver age o f all c onn ec t ed c ell s1.195 (a)It is a c ceptable f or t he electr ol yte le vel to temp ora rily increase ab o ve the specified maxim um level during equalizing c harg es pr o vi ded iti s not overf lowing.(b)C o r rectedf or ele ctr ol yte tempe rature and le ve l.Lev el co r rect ion i s n o t requ ired,h owev e r, w hen batterycharg in g is<2 amps when on fl oat charge f o r vital batteries and<1.0ampf or DG batt e rie s.(c)A batt eryc harg ing current o f<2 amps when o n f l oat charge f o r v it al batter ies an d<1.0ampf or DG b atter i es i s a c ceptab le f orm e etin g s p ecific gra vi ty lim its followinga batt e ry r echarge , f oram aximum o f 3 1 days.When cha rging cur rent i s usedt o sa ti sf y spec i fic g ravi ty requi remen ts , specif ic g ra vity o f ea ch c on nected c e l l shal l b e me asured pri ort o expirati on o f the 3 1 daya llo w anc e.W att s Bar-Unit 1 3.8-3 6
"'.'.H.,;;,]C.ll{*'.'t<:/r:.I__.'___f i:..*********t v-" I I"S.'(:j**'"*:..-" , ,.:...;:: '.1*..*:*,;';**,.,*".: 1..:.;*",*-*6'1: , 8*:..).S f)*..,\.*oj*..c:.:: 6_.i'**..****:]******..;***4***,.*-.?2 lit.*2 ,;.."J*"b**2;,.2'J..**<,**-: c.f-***.o***:.1 1**>.*;(..*'.'./T:.\I-'"\_'.y...;/-......--
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ROEXAM 1 C203C4A5B6C708C9010B 11 C12A13014C15016C 17 C18A19C20C21A22C23C24A25B26C27A28A29B 30 031C 32 B33C34B35A36B37B38039A40041042A43C44A45046C47048B49C50CWattsBar2008-301Written
Examination
Key:
51 A 52 C 53 0 54 A 55 A 56 A 57 0 58 0 59 C 60 0 61 C 62 A 63 C 64 C 65 0 66 A 67 0 68 0 69 C 70 C 71 B 72 0 73 B 74 C 75 BSROEXAM 76 C 77 B 78 A 79 0 80 0 81 B 82 B 83 0 84 C 85 B 86 0 87 C 88 0 89 0 90 0 91 0 92 C 93 C 94 C 95 A 96 A 97 A 98 C 99 0 100 B