ML082110233
| ML082110233 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/30/2008 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-338/08-301, 50-339/08-301, ES-401 IR-08-301 | |
| Download: ML082110233 (129) | |
See also: IR 05000338/2008301
Text
Final Submittal(BluePaper)
AJ 0 H
Senior Operator Written Examination
aI L/ST OF It!/fsHAJS-WEL
ES-401 Name: Site-SpecificSROWritten
Examination
Cover Sheet u.s.Nuclear Regulatory
Commission
Site-SpecificSROWritten
Examination
Applicant InformationFormES-401-8
Date: June 24, 2008 Facility/Unit:
North Anna/Units
1&2 Region: Start Time: II Reactor Type: Westinghouse
Finish Time: InstructionsUsethe answer sheets provided to document your answers.Staple this cover sheetontopofthe
answer sheets.Topassthe examination
you must achieveafinal gradeofatleast 80.00 percent overall, with 70.00 percent or betteronthe SRO-only items if given in conjunction
with the RO exam;SRO-only exams given alone requireafinal grade of 80.00 percenttopass.You
have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination,and3 hoursifyouareonly
takingtheSROportion.
Applicant Certification
All work done on this examinationismyown.Ihave
neither given nor received aid.Applicant's
Signature Results RO/SRO-Only/Total
Examination
Values/--/--Points Applicant's
Scores/--/--Points Applicant's
Grade/--/--Percent
NORTH ANNA2008RO/SROWRITTENEXAMLISTOF KIA's&EXAM ANSWERKEY*FINALPage1 of 3 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19-20 21 22 23 24 25 26.27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 4400102.4.31I
003 A4.07 2 004 G2.2.3 3005Kl,064 866 Iet.82 5007A4JO6 007 K3.01 7 008AA2.248 008 K4.019 00902.4.4 10 010 K5.01 11 011 EK2.02 12 012 K6.04 13013AI.0714
013 K4.lS 15 015 AK2.0116 016Kl.0217017A4.0218
022 A2.06 19 022 AK3.03 20 022 KI.04 21025AAI.1222026A4.0123
026 AA2.01 24 026K2.0125 02702.2.4226
028 K3.0127 029 EKl.05 28 029 K4.03 29 032AK3.0130 033 K4.05 31 036 AAI.OI'32 039 02.1.3233 041 K6.03 34 054 AK3.01 35 055 A3.03 36055EAI.0637
056 AA2.72 38 057 02.4.45 39 058 AKL0140 059 Kl.02 41 060 AA2.05 42061G2.4.343
061 K2.0144
NORTH ANNA2008RO/SROWRITTENEXAMLISTOF KIA's&EXAM ANSWERKEY*FINALPage2 of 3 45 062 G2.1.27 45 A 46 062 K3.03 46 A 47 063 K4.0147 D 48 064
48 D 49 065 AK3.03 49 B 50 071A2.0250 A 51073AI.Ol51
D 52 013 KS.02 52 D 53 976
S3 C Pt.L.£'r£b
54 076 AK2.01 54 C 55 077 AAt.Ol 55 D S6 078 A4.0156 C 57 078 K4.03 57 A 58 079 Kl.Ol 58 C 59 103 A3.0l 59 D 60 E03EAI.260 D 61 EOS EIO.4 61 D 62 EA2.162 D 63 E12 EK2..163 C 64E15EK2.164
D 65 E16 EIG.165 A 66G2.1.2066 A 67 G2.1.3767 C 68 02.1.41 68 D 69 G2,,2.169 A 70 02.2.3970 A 71 02.2.771 B 72 02.3.1572 C 73 02.3.473 C 74 02.4.3274 B 75 02.4.975 A 76005AA2.0276
A 7700502.2.4077
D 78006A2.0378
D 79001G2.2.4479
C 80 008 02.4.8 80 B 81012A2.04 81 D'82 017 A2.02 82 B 83 025 AA2.03 83 C 84 026 02.1.784 C 027 02.2.25 85 A 86 034A2.0386 B 87 038 EA2.I5 87 A 88 051 02.2.44 88 C
NORTH ANNA 2008 RO/SRO WRITTEN EXAMLISTOF KIA's&EXAM ANSWER KEY*FINALPage3of389056G2.2.368990059 G7.1.23 9091061AA2.049192062AA2.059293E1302.4.209394G2.1.494
95 02.1.6959602.2.11 969702.2.35 97 98 02.3.69899G2.4.2799
100 02.4.6 100 A C D-B-A A B B-9-B B A B A
NAME_NorthAnnaPowerStation2008SROExam
1.Giventhe following:*Duringa Unit1load reduction for 1-PT-34.3, Turbine Valve FreedomTest,the following alarm is received:*1A-D1, ROD CONTROL URGENT FAILURE*The Ramphasbeenheldand
power is approximately
93%.*Taveis2.5 0F higherthanTref.Investigation
reveals that a Logic Cabinet Oscillator
Failure has occurred.WhichONEofthe following describeshowthis failure will affecttheRod Control System, including the requiredactionin accordancewiththe annunciator
response procedure?A.Rod motion is NOT inhibited in'Bank Select';adjust Turbineloadoruserodsin
Bank Select to match TavetoTref.B.Allrod motion is inhibited;
adjust Turbine load ONLY to match TavetoTref.C.Allrod motion is inhibited;
adjust Turbineloador adjustRCSboron concentration
to match TavetoTref.D.Rod motion is NOT inhibited in'Bank Select';userodsin Bank Select ONLY to match Tave to Tref.1
NorthAnnaPowerStation2008SROExam
2.Giventhe following:Unit1 cooldown and depressurizationisin progress for refueling.
RCS temperatureis195 degreesFandslowly
decreasing.
RCS pressureis360psigandslowly
decreasing."A"and"CRCPsarerunning.RHRisin service.Thecrew observes the following indications:
- Annunciator1C-G8,RCP1A-B-CSEALLEAK
La FLOWisreceived.
Sealleakoff
flowonallthreeRCPsis
approximately0.7gpmandslowly
decreasing.*AllRCP Pump Radial Bearing temperatures
are approximately
130 degreesFandstable.*AllRCPSeal
Water outlet temperatures
are approximately
160 degreesFand stable.RCP standpipe alarmsareallCLEAR.
WhichONEofthe following is correct concerning
operation of 1-CH-HCV-1307, RCPSealBypass
Isolation Valve?A.Maintainclosedand
de-energized
to address Appendix-R
concerns.B.Maintainclosedand
de-energizedduetothe potentialforRCPsealdamage.C.Energizeandopenthe
valve to prevent overheatingthe#1seals.D.Energizeandopenthe
valve to prevent overheating
pumpradialbearing.
2
NorthAnnaPowerStation2008SROExam
3.WhichONEofthe following describes a NORMALUnit2 BAST alignment?A.'C'BAST through 1-CH-P-2DtoUnit2BoricAcidFiltertoUnit2
BIT/Blender.B.'A'BAST through 1-CH-P-2AtoUnit2BoricAcidFiltertoUnit2
BIT/Blender.C.'C'BAST through 1-CH-P-2D throughrecircvalve
1-CH-HCV-11
04 ONLYandbackto'C'BAST.D.'B'BAST through 1-CH-P-2AtoUnit2BoricAcidFiltertoUnit2
BIT/Blender.
3
NorthAnnaPowerStation2008SROExam
4.Giventhefollowing:*Unit1isin
Mode 6.*Theunithasbeen
shutdownfor11days.*Cavitylevelis22feetabovethereactorvesselflange.*RCS temperatureis109 degrees F.*RHRLoop1Aisinservice.WhichONEofthe
followingistheMINIMUMRHRflow
requirementbasedonthese
plant conditions, includingthereasonforthis
minimum flow requirement, in accordance
with 1-0P-14.1, Residual Heat Removal?A.2500GPM;
preventsflowinduced
chatteronSI Accumulator
check valves.B.3000GPM;
satisfies Technical Specification
minimum flow requirementsinMode6.C.3000GPM;
preventsflowinduced
chatteronSI Accumulatorcheckvalves.D.2500GPM;
satisfies Technical Specification
minimum flow requirementsinMode6.4
NorthAnnaPowerStation2008SROExam
5.Giventhe following:*Unit1isin
Mode4withaplantcooldowntoMode5in
progress.*RCS Pressureis720psig.*RCS temperature
is 325°F.WhichONEofthe following states the power supply to 1-SI-MOV-1865A,'A'Accumulator
Discharge IsolationValve,anditsrequired
breaker positionforthecurrent
plant conditions?480VoltMCC...A.1J1;breakerisclosed.B.1H1;breakerisopen.C.1H1;breakerisclosed.D.1J1;breakerisopen.5
NorthAnnaPowerStation2008SROExam
6.Giventhe following:*Unit1isin
Mode 3.PRTlevelis
740/0 and INCREASING
SLOWLY.PRT pressureis12psigand
INCREASING
SLOWLY.PRT temperature
is 132°F and INCREASING
SLOWLY.*The following annunciatorsareLIT:1B-H1, PRZ RELIEF TK HI TEMP*1B-G2, PRZ SAFETY WLINEHI TEMP1B-H2, PRZ POWER RELIEFLINEHI TEMP*Acoustic monitor indications
are NORMAL.WhichONEofthe following identifies
the cause of the conditions
above, and includes the methodusedto identify the affected component in accordance
with annunciator
response procedures?
A.Pressurizer
PORV leaking by;Check tailpipe temperature
indication
to determine which PORV is leaking.B.Pressurizer
Safety Valve leaking by;Check tailpipe temperature
indication
to determine which Safety Valveisleaking.
C.Pressurizer
PORV leaking by;Close block valves one-at-a-time
to determine which PORV is leaking.D.Pressurizer
Safety Valve leaking by;Check tailpipe temperatureswitha contact pyrometer to determine which Safety Valve is leaking.6
NorthAnnaPowerStation2008SROExam
7.Giventhefollowing:*Unit1wasinitiallyat100
%powerattheendofcorelife.FuelfailureshaveresultedinincreasedRCSactivity(stillwithinTechSpec
limits).A spurious SafetyInjection(SI)occurred.OnetrainofSIfailedtoresetfromthecontrolroom.*MultiplePRZR
PORVliftsoccurredduringtherecovery.PRTpressureis115psig.WhichONEofthefollowing
identifiesthecurrent
conditionsinthe Containmentincludingtheraditation
monitor indicationsintheMainControlRoom?
A.ContainmentSumplevelconstant;
Containment
Particulate
and Gaseous Radiation Monitors constant.B.ContainmentSumplevelincreasing;
Containment
Particulate
and Gaseous Radiation Monitors increasing.
C.ContainmentSumplevelincreasing;
ContainmentHighRangeradiationMonitorsconstant.
D.ContainmentSumplevelincreasing;
ContainmentHighRangeRadiationMonitorsincreasing.
7
NorthAnnaPowerStation2008SROExam
8.Giventhefollowing:*AreactortriphasoccurredonUnit1.SafetyInjectionisactuated.RCSpressureis1200psig.
Containmentpressurehaspeakedat16psiaandisslowlytrendingdown.
Pressurizerlevelis 100%*Thecrewis performing1-E-0,ReactorTriporSafetyInjection.WhichONEofthefollowing
describesthemethodusedtocontrolRCS
temperatureandthe approximateMainSteampressure
maintained?
A.CondenserSteamDumps;1035psig.B.SGPORVs;1005psig.C.SGPORVs;1035psig.
D.CondenserSteamDumps;1005psig.
8
NorthAnnaPowerStation2008SROExam
9.Giventhe following:*Unit1isat
100%power.CC Pump1Ais runningandCCPump1Bisin
standby.*4160VBus1H
normal feeder is inadvertantly
opened.WhichONEofthe following describes the AUTOMATIC operationofCC Pumpsforthis event?A.CCPump1B
starts15to20 seconds afterBus1His reenergized;CCPump1AdoesNOTre-start.B.CCPump1B
startswhenBus1His
deenergized;
CC Pump 1A startsassoonasBus1His reenergized.C.CCPump1B
starts15to20 seconds afterBus1His reenergized;CCPump1Astarts15to20
seconds afterBus1His reenergized.D.CCPump1B
startswhenBus1His
deenergized;
CC Pump 1A restarts15to20 seconds afterBus1His reenergized.
9
NorthAnnaPowerStation2008SROExam
10.Giventhefollowing:*ALOCAhasoccurred.*Thecrewis
performing1-E-1,LossofReactoror
Secondary Coolant.*Thefollowing
conditions
exist:*AllSG pressures-930psigandslowlytrendingdown.*AllSGlevels-beingcontrolledat
42%NR.PZRlevel-off-scale high.Containment
Pressure-23psia.RWSTlevel-32%anddecreasingat1%every4
minutes.RCS pressure-1000psigandstable.CoreExitTCs-500
degrees F.RVLISFullRangeindication74%.Basedonthese
indications,whichONEofthefollowing
procedureentryrequirementsaremet?A.1-ES-1.3, TransfertoColdLegRecirculationB.1-ES-1.2, Post-LOCA Cooldown and DepressurizationC.1-ES-1.1,SI
TerminationD.1-FR-C.2, ResponsetoDegradedCoreCooling
10
NorthAnnaPowerStation2008SROExam
11.Giventhefollowing:TheRCSissolidinMode5.Thecrewispreparingtodrawabubblein
accordance
with 1-0P-1.1, UnitStartupFromMode5AtLessThan140DegreesFToMode5AtLessThan200DegreesF.PZRpressureis
approximately325psig.PZR temperatureis335degreesF.
RCS temperatureis180 degrees F.AssumingPZRHeatuprateisatthe
administrativelimitof 1-0P-1.1, approximatelyhowlongwillittaketoreachsaturationconditionsinthepressurizer,andwhatactionwillberequiredwhensaturation
conditionsarereached?A.60minutes;theletdown
backpressurecontrolvalve
setpointwillbe increased.
B.30minutes;letdownflowwillbemanuallyincreased.C.60minutes;letdownflowwillbemanuallyincreased.D.30minutes;theletdown
backpressurecontrolvalve
setpointwillbe increased.
11
NorthAnnaPowerStation2008SROExam
12.Giventhe following:*ALarge Break LOCA has occurredonUnit1.*Thecrewhas
completed transition
to 1-ES-1.3, TransfertoColdLeg Recirculation.
- RWSTlevelis 14°A>.Giventhese
current plant conditions,whichONE of the following identifiestherequiredECCSand Charging pump alignment aftertheinitial
swapovertoColdLeg Recirculation
is performed in accordance
with 1-ES-1.3?A.LowHeadSI
Pump flowing to Charging pumps ONLY;ChargingPumpsuctionfromLHSIPumps.B.LowHeadSI
Pump suction from Containment
Sump;Charging Pump suction from RWST.C.LowHeadSI
Pump suction from Containment
Sump;ChargingPumpsuctionfromLHSIPumps.D.LowHeadSI
Pump flowing to Charging pumps ONLY;ChargingPumpsuctionfrom
RWST.12
NorthAnnaPowerStation2008SROExam
13.Giventhefollowing:*Aplantloadreductionisinprogress.*TurbineFirstStagePressureChannel, 1-MS-PT-1446,sticksat*Reactor poweriscurrently8%.WhichONEofthefollowing
identifiestheRPSpermissiveaffectedbythis
transmitterfailure,includingtheMINIMUM
numberofRCPs,whichiflost,wouldcauseaReactor
Trip?A.P-8cannotbe
satisfied;thereactorwouldtriponlossof2RCPs.B.P-7cannotbe
satisfied;thereactorwouldtriponlossofONLY1RCP.C.P-7cannotbe
satisfied;thereactorwouldtriponlossof2RCPs.D.P-8cannotbe
satisfied;thereactorwouldtriponlossofONLY1RCP.
13
NorthAnnaPowerStation2008SROExam
14.Aneventhas
occurredonUnit1resultingincore
damage.Containment
pressurepeakedat28psia.
Containment
radiationpeakedat 2E+5R/hr.Current Plant parametersareasfollows:*RCS temperature
is slowly trending down.*AllSGsare
150/0 NarrowRangeandrising.
- AFWflowtoeachSGis150gpm.
- Containment
pressureis16psiaandslowly
trending down.*Containment
radiationis1 E+4R/hrandslowly trending down.WhichONEofthe
following identifies
the AFW flow requirements
in accordance
with 1-E-0, ReactorTripor SafetyInjection,andthe
Adverse Containment
criteria?A.AFWmaybe reducedto50gpmtoeachSGsince
Containment
pressure has decreasedtothe current value.B.AFWmaybe reducedto50gpmtoeachSGsince
Containmentradiationhas
decreasedtothe current value.C.Total AFW flow must be maintained>340gpm becauseofthe Containment
pressure transient.D.Total AFW flow must be maintained>340gpm becauseofthe Containment
radiation transient.
14
15.NorthAnnaPowerStation2008SROExam*TheUnitisat
100%power.*A failure of a semi-automatic
testerboardhas occurredintheSolid
State Protection
System resultingina General Warning condition.
WhichONEofthe following describeshowthe system is designed for the operator to identify the condition and determine the affected Train?A.A common Safeguards
Trouble annunciator
is providedinthe control room;RED GENERAL WARNING lightinthe affected train's logic cabinetwillbe extinguished.
B.Train-specific
Safeguards
Trouble annunciators
are providedinthe control room;RED GENERAL WARNING lightinthe affected train's logic cabinetwillbe extinguished.
c.A common Safeguards
Trouble annunciator
is providedinthe control room;RED GENERAL WARNING lightinthe affected train's logic cabinetwillbeLIT.
D.Train-specific
Safeguards
Trouble annunciators
are providedinthe control room;RED GENERAL WARNING lightinthe affected train's logic cabinetwillbeLIT.
15
NorthAnnaPowerStation2008SROExam
16.Giventhefollowing:Unit1isat100%power.*Thefollowingalarmisreceived:1C-G7,RCP1A-B-CSEALLEAKHI
FLOWRCP1BSeal Leakoffflowindicates6GPM.*RCP1B No.1SealDP indicates220psidandstable.
- Annunciator1C-G2,RCP1B
STANDPIPEHILEVELisNOTLIT.
- SealleakoffhasloweredonRCP1Aand1C.SealReturn
temperatureisrisingslowly.WhichONEofthefollowing
identifiestheRCPsealproblem,includingtherequiredactionsin accordancewith1-AP-33.1,Reactor
CoolantPumpSealFailure?A.RCP#1seal;
monitorRCPbearing
temperaturesandinitiateaplantshutdowntoHotStandby.B.RCP#2seal;tripthereactor,triptheRCP,andisolate
sealleakoffwithin5minutes.C.RCP#1seal;tripthereactor,tripthe
Rep,andisolateseal
leakoffwithin5minutes.D.RCP#2seal;
monitorRCPbearing
temperaturesandinitiateaplant
shutdowntoHotStandby.
16
17.NorthAnnaPowerStation2008SROExamTheUnitis currentlyat100%andstable.Control
group heaters are operatingproperlyandone
additionalsetofPRZRbackup
heatersarelockedon.
WhichONEofthe following malfunctions
can occur WITHOUT affectingPRZRheater
status regardlessofthe positionofthe Pressurizer
Level Control selector switch?A.PRZRlevel
ChanneI1-RC-LT-460failingLOW.B.PRZRlevel
Channel 1-RC-LT-459failingHIGH.C.PRZRlevel
ChanneI1-RC-LT-459failingLOW.D.PRZRlevel
ChanneI1-RC-LT-460failingHIGH.
17
NorthAnnaPowerStation2008SROExam
18.Given the following:*A LOCA has occurred on Unit 1.1A Charging Pump is tripped.*1B Charging Pump is running.*BOTH LHSI Pumps are tripped.RCPs are running.RCS pressure is 1600psigand lowering.*Containment
pressure peakedat21psiaandis
now slowly trending down.Core Exit TICsare545 degrees F.Which ONE of the following identifies
the requirement
for operation ofRCPsin accordance
with 1-E-0, Reactor Trip or Safety Injection, including the reason?A.Leave RCPs running because forced circulation
provides sufficient
core cooling.B.Stop RCPs because continued operation will result in damagetothe RCPsdueto loss of cooling water.C.Stop RCPs because an inadequate
core cooling condition could developifRCPs were tripped or lost laterinthe event.D.Leave RCPs running because ECCS flowisinadeq-uateto
ensure adequate core cooling.18
NorthAnnaPowerStation2008SROExam
19.Giventhefollowing:*Unit1isat
1000/0 power.*The Mechanical
Chillerhastrippedand
cannotberestarted.*Thecrew enters1-AP-35,Lossof
Containment
Air Recirculation
Cooling.WhichONEofthefollowing
identifies
the Containment
temperaturethatrequiresenteringtheaction
statementforTS3.6.5, Containment
Air Temperature,andalsoidentifiestherequiredactionstobetakenfortheseplant
conditions
in accordance
with 1-AP-35?A.115degreesF;
ensure ContainmentAirRecircFansarerunningwith
backdraftdampersclosed.B.105degreesF;ensuresteamchillerrunningoralignService
Water to ContainmentAirRecircFans.C.105degreesF;ensure
ContainmentAirRecircFansarerunningwith
backdraftdampersclosed.D.115degreesF;
ensuresteamchillerrunningoralignService
Water to ContainmentAirRecircFans.
19
NorthAnnaPowerStation2008SROExam
20.Giventhefollowing:Unit1isat 100°Jlc>powerfollowingarefuelingoutage.*ThecrewhasisolatedaLetdownlineleakin
accordancewith1-AP-16, Increasing
PrimaryPlantLeakage.Thecrewis preparingtoplaceExcessLetdowninservice.ExcessLetdownwillbealignedtotheVCT.WhichONEofthe
following identifies1)anExcessLetdownLineuprestrictionand2)thereasonwhy
reactor powermustbemonitoredwhenplacing
excessletdowninservicein accordance
with 1-0P-8.5,OperationofExcess
Letdown?A.Flowthrough
ONLYoneloopdraintopreventthe
possibility
of bypassing 81flowtothe2intactloopsinadesignbasisaccident;adilutionmay
occurdueto lower boron concentrationsintheExcessLetdown
piping.B.ExcessLetdown
PressuremustNOTexceed75psigto
prevent overpressurizingtheVCT;adilutionmay
occurdueto lower boron concentrationsintheExcessLetdown
piping.C.ExcessLetdown
PressuremustNOTexceed75psigto
prevent overpressurizingtheVCT;aborationmay
occurdueto higher boron concentrationsintheExcessLetdown
piping.D.Flowthrough
ONLYoneloopdraintopreventthe
possibility
of bypassing 81flowtothe2intactloopsinadesignbasisaccident;aborationmay
occurdueto higher boron concentrationsinthe Excess Letdown piping.20
NorthAnnaPowerStation2008SROExam
21.BothUnitsareat100%.*AfaultontheUnit2BstationservicebusresultsinaMain
Generator Lockout and Reactor Trip.*AllUnit2 Station Service Busses are deenergizedduetothe feeder breaker to 2B Station Servicebusfailingtoopenonthefault.WhichONEofthe
following describes the status of ContainmentcoolingtotheUnits?
A.Containment
Air RecircFansremainrunningonBOTHUnits;Chilled
waterflowto Containment
Air RecircFansislostonUnit2ONLY.
B.Containment
Air RecircFansremainrunningonBOTHUnits;Chilled
waterflowto Containment
Air RecircFansislostonBOTHUnits.
C.Containment
Air RecircFanstriponUnit2;Chilled
water flow to Containment
AirRecircFansislostonUnit2ONLY.
D.Containment
Air RecircFanstriponUnit2;Chilled
water flow to Containment
AirRecircFansislostonBOTHUnits.
21
NorthAnnaPowerStation2008SROExam
22.Giventhe following:Unit1has just enteredMode4withcooldownto
Mode5inprogress.*RHRPump1Aisin
service.TheOATCnotesthe
following:RHRPump1A motor amps indicate10andstable.
1-RH-FCV-1605
in automatic indicates 100 0/0 demand.WhichONEofthe following identifiesthestatusofthe
1-RH-FCV-1605,RHRHeat EXchanger Bypass Valve AND predictsthetrendonCoreExit
TCs?A.1-RH-FCV-1605
operating as designed;CoreExitTCsstable.
B.1-RH-FCV-1605
failed;CoreExitTCs
lowering.C.1-RH-FCV-1605
failed;CoreExitTCs
increasing.
D.1-RH-FCV-1605
operating as designed;CoreExitTCs
increasing.
22
NorthAnnaPowerStation2008SROExam
23.Giventhe following:*A reactortripand safety injection has occurred.*RCS pressureis1000psigandstable.
- Containment
pressureis23psiaandrisingslowly.*Thecrewis
performing
1-E-0, ReactorTripor Safety Injection.
WhichONEofthe following describes the appropriate
operatoractionandthe
SEQUENCEofthe action required?A.COAisnot
required, however QuenchSprayis required;start Quench Spray Pumpsandthenopen
Quench Spray discharge valves.B.COAis required;manually actuateCOA,stopRCPs, verify Quench Spray running, and verify Containment
IsolationPhaseB.C.COAisnot
required, however QuenchSprayis required;open Quench Spray Discharge Valvesandthen start Quench Spray Pumps.O.COAisrequired;
manually actuateCOA,stopCC
pumps, verify Quench Spray running, verify Containment
Isolation PhaseB,andstopRCPs.
23
NorthAnnaPowerStation2008SROExam
24.Giventhe following:*Theunitis
operatingat1 00%power.*CCSurge Tank level indicationon1-CC-LI-101is
500/0andlowering.WhichONE(1)ofthe
followingisapossiblesourceoftheleakandthesourceofwater
for maintaining
CC System inventory?
A.Non-RegenerativeHeatExchanger;
Condensate
System B.Non-RegenerativeHeatExchanger;PG
waterC.1ACCHeat
Exchanger;
Condensate
SystemD.1ACCHeat
Exchanger;
PG water 24
NorthAnnaPowerStation2008SROExam
25.GiventhefollowingonUnit1:
ReactorTripduetoaLOCA.
- SafetyInjectionwas
actuated11minutesago.*COAwas automatically
actuated7minutesago.*RCS pressureis1125psig.
- RWSTlevelis 720/0andlowering.WhichONEofthe
following describes the operationalstatusofInsideRecirculationSprayPump1-RS-P-1B?A.NOTrunning;
power is available directlyfrom4160voltbus1J.B.Running;
power is supplied directlyfrom480voltbus1J1.C.Running, power is supplied directlyfrom4160voltbus1J.O.NOTrunning;
power is available directlyfrom480voltbus1J1.
25
NorthAnnaPowerStation2008SROExam
26.Giventhefollowing:Unit1is operatingat100%power.*An instrumentfailurecausesPORV
1-RC-PCV-1455Ctolift.RCSPressureisrecoveringatamuch
slowerratethanexpected.
The operatorclosesthePORVBlockValve, 1-RC-MOV-1536,andpressureisnow2100psigandincreasingasexpected.*Allother equipmentappearstobeoperatingnormally.WhichONE(1)ofthefollowing
describestheaction(s)requiredwithinONEhourin
accordance
with Technical Specifications?A.Maintainclosedandmaintainpowerto
1-RC-MOV-1536.B.RestoreRCSpressuretowithinlimitsoftheCOLR.C.VerifyP-11
interlockisinrequiredstateforexistingunitcondition..
D.Maintainclosedandremove
power from 1-RC-MOV-1536.
26
NorthAnnaPowerStation2008SROExam
27.Giventhefollowing:Unit1wasinitiallyat100
0/0.Unit1 experiencedalargebreakLOCAThecrewplaced1-HC-HC-1,Hydrogen
RecombinerinserviceonUnit1
Containment.*The Recombinertrippedwithin5minutesandcouldnotberestarted.
Hydrogen concentrationisnowGiventheseplant
conditionswhichONEofthefollowing
identifiestherequired
operatorresponsein
accordancewith1-E-1,Lossof
Reactor or Secondary Coolant?A.Place2-HC-HC-1,HydrogenRecombiner,inserviceonUnit1
Containment.B.Place1-HC-F-1, Containment
AtmospherePurgeBlower,inserviceonUnit1
Containment.C.Place2-HC-F-1, Containment
AtmospherePurgeBlower,inserviceonUnit1
Containment.D.VentUnit-1
containmentthroughtheAuxiliaryBuildingIodineFilters.
27
NorthAnnaPowerStation2008SROExam
28.Duringan ATWS at 100 D A>ReactorPower,EOL conditions,whichONEofthefollowing
actions will insert the MOST negative reactivitywithinthe FIRST 30 secondsofthe ATWS?A.Initiationof
Emergency BorationB.Manual Turbine Trip C.Automatic Control Rod InsertionD.Manual ControlRodInsertion
28
NorthAnnaPowerStation2008SROExam
29.Giventhefollowing:BothunitsareinMode5.isinprogressoneachunitin
preparation
for Containment
entrv.wrlh
bo+ll pvr?>e stJpply*to..i1S'I'Vf\(\,Yl3'Unit1 ManipulatorCraneAreaRadiation
MonitorRM-162indicationisrising.Unit1 ContainmentParticulateandGaseousRadiationMonitors,RM-159and160areinalarm.Unit2 containment
conditionsarenormal.WhichONEofthefollowingpredictsthefinalstatusof
ContainmentPurgeafterALL
automatic actuationshavetakenplace?A.PurgeSupplyFans
1-HV-F-4Aand1-HV-F-4BNOTrunning;
ContainmentPurgeSupplyisolationvalvesclosedonBOTHunits.B.PurgeSupplyFans
1-HV-F-4Aand1-HV-F-4Bbothrunning;Unit1 ContainmentPurgeSupplyisolationvalves
close.d;Unit2 ContainmentPurgeSupplyisolationvalvesopen.C.PurgeSupplyFans
1-HV-F-4Aand1-HV-F-4BNOTrunning;Unit1 ContainmentPurgeSupplyisolationvalvesclosed;Unit2 ContainmentPurgeSupplyisolationvalvesopen.D.PurgeSupplyFans
1-HV-F-4Aand1-HV-F-4Bbothrunning;
ContainmentPurgeSupplyisolationvalvesclosedonBOTHunits.
29
NorthAnnaPowerStation2008SROExam
30.Giventhefollowing
conditions:*Areactorstartupisinprogressandoperatorshave
just completedarodpull.*Both IntermediateRangechannelsindicate
approximately3E-11ampsandtrendingup.*SourceRange
ChannelN-31indicates1X10
3CPSandistrendingdownslowly.*SourceRangeChannelN-32indicates
approximately6X10 3CPSandtrendingupslowly.WhichONEofthefollowing
describestherequired
operatorresponseinaccordancewith1-AP-4.1, MalfunctionofSourceRangeNuclear
Instrumentation,andthereasonfortheresponse?A.Suspendthereactorstartup;dueto
insufficientoverlapbetweenSourceRangeand
IntermediateRangechannels.B.Continuethe
reactorstartup;theoperableSourceRangechannelisadequatetoprovideprotection
againstaborondilutionevent.C.Suspendthereactorstartup;withonlyoneSourceRangechanneloperable,there
is inadequate
protection
againstanuncontrolledrod
withdrawal.D.Continuethe
reactorstartup;theoperableSourceRangechannelisadequatetoprovideprotection
againstanuncontrolledrod
withdrawal.
30
31.NorthAnnaPowerStation2008SROExam
Operators are performingablendedmake-uptotheSpentFuelPool(SFP)
following completionofcaskloadingoperations.*Acalibration
errorresultsin 1-CH-FT-1114, PG Water to blender flow transmitterindicatinglessthantheactualflowrate.WhichONEofthefollowingpredictsthe
effectonboron concentrationoftheblendedflowbasedontheseplantconditions,and
identifies
theTechnicalSpecificationminimumrequiredboron
concentrationfortheSFP?A.Boron concentrationoftheblendedflowwillbe
greaterthanthecalculatedvalue;2600ppm.B.Boron concentrationoftheblendedflowwillbelessthanthecalculatedvalue;2500ppm.C.Boron concentrationoftheblendedflowwillbe
greaterthanthecalculatedvalue;2500ppm.D.Boron concentrationoftheblendedflowwillbelessthanthecalculatedvalue;2600ppm.31
NorthAnnaPowerStation2008SROExam
32.Giventhe following:Unit1isin Mode6withCore offload in progress.*Afuel assembly becomes visibly damaged when removedfromthecore.
Containment
radiationisrisingslowly.*The assembly is returnedtoitslocation.
Containment
evacuationhasbeeninitiated.
WhichONEofthe following identifies1)the expected indicationsand2)thecrew's
response in accordancewithO-AP-5.2,MGP
Radiation Monitoring
System?A.Vent Stack'B'Radiation Monitor indication
increases;
Verify Containment
Purge Exhaust automatically
isolates when Vent Stack'B'Radiation Monitor exceeds alarm setpoint.B.Vent Stack'A'Radiation Monitor indication
increases;
Verify Containment
Purge Exhaust automatically
isolates when Vent Stack'A'Radiation Monitor exceeds alarm setpoint.C.Vent Stack'A'Radiation Monitor indication
increases;
Manually divert Containment
Purge Exhaust through the Auxiliary Building Iodine Filters D.Vent Stack'B'Radiation Monitor indication
increases;
Manually divert Containment
Purge Exhaust through the Auxiliary Building Iodine Filters.32
NorthAnnaPowerStation2008SROExam
33.WhichONEofthe following describesthereasonfor
equalizing
Main Steam pressure when openingaMain Steam NRV thathasbeen closed?A.Prevent damagetovalve internalsdueto excessiveDPwhen openingtheNRV.B.Prevent excessiveswellofSG volume.C.Prevent themal overload of breaker for NRVdueto excessiveDPwhenopeningthe
NRV.D.Prevent inadvertent
Hi Steam Line Differential
Pressure SI.33
NorthAnnaPowerStation2008SROExam
34.Giventhe following:Unit1isat100
%power.*Rod ControlisinMANUAL.*All other controlsarein AUTO.*A Turbine control valve failureresultsinaload
rejection.*Tavg-Tref deviation indicates 11 degrees F.*1M-D4, STEAM DUMP ARMED, is illuminated.
WhichONEofthe following describesSteamDump response?A.Two banks of steam dumps are modulating
open;Two banks of steam dumpsareclosed.B.Onebank of steam dumps is tripped open;One bank of steam dumps is modulating
open.C.Fourbanks
of steam dumpsaretrippedopen.D.Two banks of steam dumps are tripped open;One bank of steam dumps is modulating
open.34
NorthAnnaPowerStation2008SROExam
35.Giventhefollowing:
Reactor power is 75°A>.1B MFWPumpisoutofserviceforpumpcouplingrepairs.*Thefollowing
alarmsarereceived:*1F-A4,MAINFDPPSDISCHHDRLOPRESS1F-A5,MAINFDPP1A-1B-1CAUTOTRIP
1 F-F1/F2/F3, SG 1N1B/1CLEVELERROR*1 F-D1/D2/D3,STMGEN 1A11B/1CFW<STrvl
FLOW CH III-IV*TheBOP determinesthat1C MFWPumpistripped.*Thecrew enters1-AP-31,LossofFeedwater.
WhichONEofthe following describestheactionrequired,andreasonfortheaction?A.Reduceload;
prevent operating MFW pump motor windings from overheating
due to excessive current.B.Tripthereactor;
prevents damagetooperatingMain
FeedwaterPumpduetopumprunoutflowand
cavitation.C.Tripthereactor;
prevents a challengetothe Reactor ProtectionSystemfromlossof
secondaryheatsink.D.Reduceload;
reducessteamflowtowithinthecapacityofthe
operating MFW pump.35
36.NorthAnnaPowerStation2008SROExam
Initial Conditions:*ASteam GeneratorTubeLeakisoccurringonUnit1.*Thecrewis
entering1-AP-24,Steam
GeneratorTubeLeak.Condenser Air Ejector Radiation Monitor1-SV-RM-121isinHi-Hialarm.
Current conditions:
- Reactor Trip.Safety Injection is actuated.*Thecrewis
performingactionsof 1-E-O, ReactorTripor Safety Injection.WhichONEofthe
following describes the alignmentofthe CondenserAirEjectorsteamsupplyand
exhaustforthecurrent
conditions?
.A.Exhaust isolatedonPhaseAisolation;steamsupplytoair
ejectorsisolatedonPhaseA isolation.B.Exhaust diverted to ContainmentonPhaseAisolation;steam
supplytoairejectorsisolatedonPhaseAisolation.C.Exhaust diverted to ContainmentonHI-HIradiation;steam
supplytoairejectorsisolatedonHI-HIradiation.D.Exhaust isolatedonHI-HIradiation;steamsupplytoair
ejectorsisolatedonHI-HI
radiation.
36
NorthAnnaPowerStation2008SROExam
37.Given the following:*A loss of all AC Power has occurred.*The crew is performing
actions of 1-ECA-O.O, Loss of All AC Power.1H EDG has failed and CANNOT be restarted.
- The crew is performing
1-ECA-O.O, Attachment
4, Attempting
to restore power to1H(1J)Emergency Bus.*Attempts to start EDG1Jarein progress.RCP Seal Water Outlet temperature
is 200°F and rising at 20F per minute.Which ONE of the following describes the action required in accordancewithECA-O.O?
A.Place1J EDG in MANUAL-LOCAL, press EMER GEN Alarm&Shutdown RESET Button, and verify Shutdown Relay Status Lightislit.After one minute, place1JEDGin MANUAL-REMOTE and determineifthe EDG starts.B.Place Charging Pumps in PTL prior to attempting
to start1J EDG in MANUALLOCAL.C.Perform Attachment
3, RCP seal isolation, prior to attempting
to start1J EDG in MANUAL-LOCAL.D.Place 1J EDG in MANUAL-REMOTE, press EMER GEN Alarm&Shutdown RESET Button, and verify Shutdown Relay Status Lightislit.After one minute, place 1J EDG in MANUAL-LOCAL and determine if the EDG starts.37
NorthAnnaPowerStation2008SROExam
38.Giventhe following:
- AFW pump 1-FW-P-2 is taggedoutto replace the overspeed trip tappet.Unit1 reactortripfrom100
%power.*Severe weather causesaLossof Off-Site power.*An electrical
faulton1HBushas
causedabus lockout.WhichONEofthe following describes the responseofthe AFW System during this event?A.1-FW-P-3B starts as soonasthe 4160 Volt emergencybusis energized;
AFWwillbe suppliedtoBSG.B.1-FW-P-3B starts approximately
20 seconds after the 4160 Volt emergencybusis energized;
AFWwillbe suppliedtoCSG.C.1-FW-P-3B starts approximately
20 seconds after the 4160 Volt emergencybusis energized;
AFWwillbe suppliedtoBSG.D.1-FW-P-3B startsassoonasthe
4160 Volt emergencybusis energized;
AFWwillbe suppliedtoCSG.38
NorthAnnaPowerStation2008SROExam
39.TheUnitisin
MODE 3 preparing to startup.Lossofvitalbus
1-1 occurred and powerhasnotyetbeen
restored.Station Emergency Manager just declared a Notification
of Unusual Event.WhichONEofthe following describes the correct response and required notifications?
A.Monitor RCP temperaturesduetolossofCCflow;
Notification
of StateandLocal authorities
is required withinthenext15 minutes.B.Monitor RCP temperaturesduetolossofCCflow;
Notification
of StateandLocal authorities
is required within the next 60 minutes.C.Monitor SG PORVsduetolossof
condenser steam dumps;Notification
of StateandLocal authorities
is required within the next 15 minutes.D.Monitor SG PORVsduetolossof
condenser steam dumps;Notification
of StateandLocal authorities
is required withinthenext60 minutes.39
NorthAnnaPowerStation2008SROExam
40.Giventhe following:*Unit1isat100
%power.*AllDCBus voltages are approximately131VDC.*The followingalarmis receivedinthecontrolroom:1H-B3, BATTERY CHGR 1-111 TROUBLE Battery Charger 1-111 DC Output breaker has tripped and CANNOTbereset.*DCBus 1-111 voltageis118voltsandlowering.
WhichONEofthe following describestheactionthatwillbetakentorestoreDCBus
1-111 in accordance
with 1-0P-26.4.3,MainStationSwing
Battery Chargers 1C-1 and1C-II Operation?A.PlaceSwing
Battery Charger1C-Iinservicewiththe
NORMAL/EQUALIZEswitchin EQUALIZE.B.PlaceSwing
Battery Charger1C-IIinservicewiththe
NORMAL/EQUALIZE
switch in NORMAL.C.PlaceSwing
Battery Charger1C-IIinservicewiththe
NORMAL/EQUALIZE
switch in EQUALIZE.D.PlaceSwing
Battery Charger1C-Iinservicewiththe
NORMAL/EQUALIZEswitchin NORMAL.40
NorthAnnaPowerStation2008SROExam
41.Giventhefollowing:Theplantisat
25°h power.*A Condensate
headerruptureoccurs,andthefollowing
conditionsarepresent:*AllMain Feedwaterpumpstripped.
10 secondslaterSGlevelsare
300/0narrowrangeandlowering.
- Reactor powerremainsat 25°h.WhichONEofthefollowing
describestheoperationofthe
ReactorProtectionSystemandthe Auxiliary Feedwater(AFW)Pumpsforthis
condition?A.Areactortrip
setpointhasNOTbeenexceeded;
AFWPumpsareNOTrunning.B.Areactortrip
setpointhasbeenexceeded;
AFWPumpsarerunning.C.Areactortrip
setpointhasNOTbeenexceeded;
AFWPumpsarerunning.D.Areactortrip
setpointhasbeenexceeded;
AFWPumpsareNOTrunning.
41
NorthAnnaPowerStation2008SROExam
42.Giventhefollowing:*Releaseof
WasteGasDecayTank1Bisinprogress.
- 1-GW-RI-178-1, Process VentNormalRangeMonitor, indicationisrising.*1-GW-RI-178-2, Process VentHighRangeMonitor, indication
is justcomingon scale.Thefollowingalarmsarereceived:*2B-A5, PROCESS VENT VNT STACK A&B LOWRADMON ALERT/RAD*2B-B5, PROCESS VENT VNT STACKA&BHIHI RADIATIONWhichONEofthefollowing
describesthestatusofthe
WasteGasDecayTankreleaselineup?A.1-GW-FCV-101AND
1-GW-PCV-117closedwhen
1-GW-RI-178-1HIradiationalarmwasreceived.B.1-GW-FCV-101remainedopenUNTIL
1-GW-RI-178-2HIradiationalarmwas
received.1-GW-PCV-117doesNOTreceiveaclosesignal.C.1-GW-FCV-101closedwhen1-GW-RI-178-1HIradiationalarmwasreceived.
1-GW-PCV-117doesNOTreceiveaclosesignal.D.1-GW-FCV-101AND
1-GW-PCV-117remainedopen
untiI1-GW-RI-178-2
HIradiationalarmwasreceived.
42
NorthAnnaPowerStation2008SROExam
43.Giventhe following:*A LOCA occurredonUnit1thirty
minutes ago.*Thecrewis
performing1-E-1,Lossof
Reactor or Secondary Coolant.*1-RM-RMS-165
and 1-RM-RMS-166, ContainmentHighRange Radiation Monitors,bothhave amberandredlights
illuminatedinthe control room.WhichONEofthe following describes the additional
indications
observedifanactualhighradiation
condition exists?A.SAFE/RESETgreenlighton
drawers LIT;UNIT1 CONT HI RANGE RADIATION TROUBLE annunciatorreceivedonUnit2.
B.SAFE/RESETgreenlighton
drawers LIT;UNIT1 CONT HI RANGE RADIATION TROUBLE annunciator
receivedonUnit1.C.SAFE/RESETgreenlighton
drawersNOTLIT;UNIT1 CONT HI RANGE RADIATION TROUBLE annunciatorreceivedonUnit2.
D.SAFE/RESET
greenlighton drawersNOTLIT;UNIT1 CONT HI RANGE RADIATION TROUBLE annunciatorreceivedonUnit1.
43
NorthAnnaPowerStation2008SROExam
44.WhichONEofthefollowingstatesthepowersuppliesto
AFWDischargeMOVs, 1-FW-MOV-100A,B,C?A.MCC1J1-2NB.1A Semi-Vital
BusC.1B Semi-Vital
Bus D.MCC1H1-2N 44
45.NorthAnnaPowerStation2008SROExam
In accordancewiththe applicable
Fire Contingency
Action (FCA)procedure, whichONEofthe following describes actionsrequiredto
maintain power supplytothe Unit-1 remote monitoring
excore neutron flux detector (channel one)followingafireinthe
given location?A.FollowingafireintheMain
Control Room, suppliedfromUnit-2vitalbusinverter2-1,whichwillbe
disconnectedfromvitalbus
2-1.B.FollowingafireinUnit-1
emergency switchgear, suppliedfromUnit-2vitalbus
inverter2-1,whichwillbe
disconnectedfromvitalbus
2-1.C.FollowingafireintheMain
Control Room, suppliedfromUnit-1vitalbus
inverter1-1,whichwillbe
disconnectedfromvitalbus
1-1.D.FollowingafireinUnit-1
emergency switchgear, suppliedfromUnit-1vitalbus
inverter1-1,whichwillbe
disconnectedfromvitalbus
1-1.45
NorthAnnaPowerStation2008SROExam
46.Giventhe following:*Both Unitsareat100%power.*AFirein RSST'A'causes an overcurrent
lockout on TransferBusD.WhichONEofthe following describes the battery chargers that are temporarily
deenergized?
A.1-111 and 1-IV B.2-1 and 2-11 c.2-111 and 2-IV D.1-land1-11
46
47.NorthAnnaPowerStation2008SROExamIfalossofBattery
Charger 1-1weretooccur,whatwouldbethe
effectontheoperationofitsassociated
inverterandthevitalDCbus?A.NOstaticswitch
automatictransfer;vitalDCbusvoltageinitially
decreases byseveralvoltsandthen
continuestodecreaseatthesamerateovertime.B.Staticswitch
automatic transferoccurs;vitalDCbusvoltageinitiallydecreasesbyseveralvoltsandthen
continuestodecreaseata
fasterrateovertime.C.Staticswitch
automatic transferoccurs;vitalDCbusvoltageinitiallydecreasesbyseveralvoltsandthen
continuestodecreaseatthesamerateovertime.D.NOstaticswitch
automatictransfer;vitalDCbusvoltageinitially
decreases byseveralvoltsandthen
continuestodecreaseata
fasterrateovertime.
47
NorthAnnaPowerStation2008SROExam
48.Giventhe following:*A lightning strike has occurredresultinginaloss
oftheNorth Anna Switchyard.*The1JEDG Battery and Battery ChargerareBOTHlost.
125 VDC Bus 1-1islost.*A spurious SI occurs.Thecrewhas
entered 1-E-O, ReactorTripor Safety Injection, and manually actuated SI.WhichONEofthe following describesthereason thatnoJTrainESF
equipment is running?A.1JEDGdid
NOT startduetolossoftheDCfueloilpump.B.1JEDG started,buttheEDG output breaker did NOT closeduetoloss ofDCfield flash capability.C.1JEDG startedandtheEDG output breakerisclosed,butno
control power is availableto1JBusload
breakers.D.1JEDGdid
NOT startduetolossof
powertoboth start circuits.48
NorthAnnaPowerStation2008SROExam
49.Unit1isoperatingat100
%power.*Thefollowingalarmisreceived:*1F-F8,SANDFLTRIASUPPLYLOPRESS.*TheOATCnotes
instrumentairpressureis85psigandrapidlydecreasing.*Thecrewinitiates1-AP-28,LOSSOF
INSTRUMENT
AIR.*InstrumentAirpressurecontinuestolower.*TheSROdirectstrippingthereactorandclosingMainSteamTripValves.WhichONEofthefollowingidentifiesthereasonformanuallyclosingtheMainSteamTripValves?A.ToavoidaHighSteamLineDeltaPsafetyinjectionduetoclosureofasinglemainsteamtripvalve.B.ToavoidaHighSteamFlowsafetyinjectionduetoclosureofasinglemainsteamtripvalve.C.ToavoidaLo-LoSGlevelreactortripduetoclosureofallmainsteamtripvalves.D.ToavoidaHighPZRPressurereactortripduetoclosureofallmainsteamtrip
valves.49
NorthAnnaPowerStation2008SROExam
50.Giventhe following:*Thecrewis
preparing to release WGDT1B.*The maximum allowed flowratepertherelease
permitis300SCFM.
WhichONEofthe following describes the preferred method for controlling
the WGDTreleaseflowratein
accordance
with 0-OP-23.2, WGDT and Waste Gas Diaphragm Compressors?
A.1-GW-FCV-101, WGDT to ProcessVent,shouldbe
placed in AUTOMATIC and adjusted to control flowrateatlessthan3SCFM.
B.1-GW-FCV-1
01, WGDT to Process Vent, should be placed in MANUAL and'adjusted to controlflowrateatlessthan3SCFM.
C.1-GW-FCV-101, WGDT to Process Vent, should be placed in AUTOMATIC and adjusted to controlflowrateat290
i:5SCFM.D.1-GW-FCV-1
01, WGDT to Process Vent, should be placed in MANUAL and adjusted to control flowrateat290 i:5SCFM.50
NorthAnnaPowerStation2008SROExam
51.Giventhe following:EachUnithasa
containmentvacuumpumprunning.
- 1-GW-RI-178-3, Process Vent particulate
radiation Monitor indication
spiked, causing an ALERTandHIGHalarmtolockin.
WhichONEofthe following describestheplant response?A.ONLYtheunit1
vacuum pump dischargevalvewill automatically
close.B.ONLYtheunit1
vacuumpumpwilltrip.C.Bothunits'
vacuum pumpswilltrip;dischargevalvesremainopen.D.Bothunits'
vacuum pump dischargevalveswill
automatically
close.51
52.NorthAnnaPowerStation2008SROExam
Initial Conditions:
Operations
notedastep increase on 1-CH-RM-128,Unit1 Reactor Coolant Letdown Monitor.*Health Physics identifiedahot spotinthe letdown piping four (4)feet from 1-CH-RM-128
detector.*General area surveytakenat 1-CH-RM-128
detectorwas60 mRem/hourpriorto flushingthehotspot.*No Radiation Monitorsinalarm.Current Conditions:Operationsflushedthehot spot and relocatedittotwo(2)
feet from 1-CH-RM-128
detector.*1-CH-RM-128
Hi alarm-LIT.*Annunciator1K-D2,Rad Monitor SystemHiRad Level-LITsolid.Basedon current conditions,whichONEofthe
following identifies
the expected general area survey at 1-CH-RM-128
detector,andalso predicts the response of Annunciator1K-D2,ifahighalarm
subsequently
occurs on 1-SV-RM-121, Condenser Air Ejector Radiation Monitor?A.120 mRem/hour;
Annunciator1K-D2will remainLITsolid.B.240 mRem/hour;
Annunciator1K-D2will remainLITsolid.C.120 mRem/hour;
Annunciator1K-D2will blinkandhornwillsounduntil
acknowledged.D.240 mRem/hour;
Annunciator1K-D2will blinkandhornwillsounduntil
acknowledged.
52
NorthAnnaPowerStation2008SROExam
53.Giventhefollowing:*Unit1isat100%power.ThreeBCfansarerunningin
SLOWspeedandthefourthisinstandby.
Computer alarmsarereceivedonseveral
componentscooledbytheBearingCoolingSystem.
Subsequently,thefollowingalarmsarereceived90
seconds apart:1A-F4,BASINTEMP
HI/LOW*1T-C1, HYDROGENTEMPORCORE
MONITORThecrew enters1-AP-19,LossofBearingCoolingWater,andverifiesaBearingCoolingPumpisrunning.WhichONEofthefollowing
describestheinitialactionrequiredin
accordance
with 1-AP-19?A.Bypass 1-BC-TCV-104, Generator Hydrogen CoolerTCV,tolowerhydrogen
temperature.B.PlaceBearingCoolinginLake-to-LakeModeandverifythe
operationoftheCirc WaterSystemto ensurecoolingrequirementsaremet.C.StartavailableBearingCoolingTowerFansorshiftfanstohighspeed;verifyBearingCooling
temperaturesaredecreasing.D.Verify Generator Hydrogen temperatureisabovethealarm
setpointandinitiateaplantloadreductionuntilthealarmisclear.
53
NorthAnnaPowerStation2008SROExam
54.Giventhe following:*Unit1isat
40°A>power.*TheBSGhas
developeda60gpdtubeleak.
- Operators are preparing to shutdowntheUnitduetofuel
failureresultingin
ReS activity increasingata steady rate.Basedon these plant conditions,whichONEofthe
following identifies
how 1-SV-RM-121, Condenser Air Ejector Radiation Monitor, and 1-MS-RI-191,"B"SGN-16 Radiation Monitor,willrespondasRCS
activity increases?
A.1-SV-RM-121
indicationwillnot change;1-MS-RI-191
indicationwillnot change.B.1-SV-RM-121
indicationwillnot change;1-MS-RI-191
indication
will increase.C.1-SV-RM-121
indication
will increase;1-MS-RI-191
indicationwillnot change.D.1-SV-RM-121
indication
will increase;1-MS-RI-191
indication
will increase.54
NorthAnnaPowerStation2008SROExam
55.Giventhefollowing:Bothunitsareat100
%power.Duetovoltageand
frequency fluctuationsonthegrid,thecrewisperforming
actions containedin0-AP-8,ResponsetoGridInstability.Thecrewhasverified
equipment operability.WhichONEofthe
following describestheoperationoftheMain
Generator VoltageRegulatorsper0-AP-8,andtheconditionthatrequiresthe
offsitepowersourcetobe
declared inoperable?A.Placevoltage
regulatorsinMANUAL;gridvoltage
decreasesto504kVB.Maintainvoltage
regulatorsinAUTO;gridvoltage
increasesto536kV c.Placevoltage
regulatorsinMANUAL;gridvoltage
increasesto536kVD.Maintainvoltage
regulatorsinAUTO;gridvoltage
decreasesto504kV 55
NorthAnnaPowerStation2008SROExam
56.WhichONE(1)ofthe
following describes the operation of Instrument
Air Compressor
"1-IA-C-1"whenitis placed in AUTO?A.Compressor
will startandrun continuouslyforan indefinite
periodoftime.Unloader valves will CLOSE when pressure dropsto103psig.
Unloader valves willOPENwhen pressurerisesto109psig.
B.Compressor
will startandrun continuouslyforan indefinite
periodoftime.Unloader valves will CLOSE when pressure dropsto98psig.Unloader valves willOPENwhen pressurerisesto106psig.
C.Compressor
will startandloadwhen
pressure dropsto98psig.Compressor
will unload when pressurerisesto106psig.
D.Compressor
will startandloadwhen
pressure dropsto103psig.
Compressor
will unload and shut down when pressure increasesto109psig.
56
NorthAnnaPowerStation2008SROExam
57.Instrument
Air Compressor1-IA-C-1hasbeenrunning
loaded for the past15minutes.
WhichONEofthe following choices completes the following sentence?Either aORawillresultinatrip
of the Air Compressor.A.LowOil Pressure;Cooling System Fault causedbylowcooling
system DPB.High Discharge Pressure;Cooling System Fault causedbyhigh pressure on surge line.C.High Discharge Pressure;Cooling System Fault causedbylowcooling
system DPD.LowOil Pressure;Cooling System Fault causedbyhigh pressure on surge line 57
NorthAnnaPowerStation2008SROExam
58.Giventhe following:*Alossof Instrument
Air is occurringonUnit1.*The immediate actions of 1-AP-28,Lossof InstrumentAir,are complete.*Instrument
Air pressureis90psigand
dropping slowly.WhichONEofthe following describes the compressor
statusandthe actiontobetakenbasedonthe
system pressure in accordance
with 1-AP-28?A.All Service Air Compressors
running and loaded;all Instrument
Air Compressors
running unloaded;Isolate Instrument
Air to Containmentbyclosing 1-IA-TV-102A
or 1-IA-TV-102B, Containment
Instrument
Air Trip Valves.B.All Service Air Compressors
running and loaded;all Instrument
Air Compressors
running unloaded;Verify Instrument
Air supplied to Containment
by verifying open 1-IA-TV-102Aand
1-IA-TV-102B, Containment
Instrument
Air Trip Valves.C.All Instrument
and Service Air Compressors
running and loaded;Isolate Instrument
Air to Containmentbyclosing 1-IA-TV-102A
or 1-IA-TV-102B, Containment
Instrument
Air Trip Valves.D.All Instrument
and Service Air Compressors
running and loaded;Verify Instrument
Air supplied to Containment
by verifying open 1-IA-TV-1 02A and 1-IA-TV-102B, Containment
Instrument
Air Trip Valves.58
NorthAnnaPowerStation2008SROExam
59.Giventhefollowing:*ALOCAhasoccurredonUnit1.*Thefollowing
conditions
exist:*RCS pressureis1700psig.
- Containmentpressurehaspeakedat
21psiaandisnowslowlydecreasing.*Thecrewis
performing1-E-0,ReactorTriporSafetyInjection.*TheROis performing
Attachment5,VerificationofPhaseAIsolation.*ThefollowingvalvesareidentifiedasOPEN:
- 1-CH-MOV-1115B,RWSTToChargingPumpsIsolation
1-CH-MOV-1289B,NormalChargingLineIsolation
- 1-IA-TV-102A, ContainmentInstrumentAirTripValve
1-SW-MOV-108A, Service WatertoCCHeat Exchanger IsolationForthecurrentplantconditions,whichONEofthefollowingvalvesmustberepositionedtoplaceitintherequiredaccident
configuration?
A.1-SW-MOV-108A
B.1-CH-MOV-1115B
C.1-IA-TV-102A
D.1-CH-MOV-1289B
59
NorthAnnaPowerStation2008SROExam
60.Giventhefollowing:*ALOCAhasoccurredonUnit1.Thecrewis performing1-ES-1.2,PostLOCACooldownandDepressurization.DuringtheSIflowreductionsequence,thefollowing
conditions
exist:*AllRCPsarestopped.*TwoChargingPumpsarerunning.*RCS pressureis1100psigandstable.*RCS SubcoolingbasedonCoreExitTCsis55°F
- Pressurizerlevelis44%.
Containmentpressureis20.9psia.WhichONEofthefollowing
describestheresponsetothese
conditionsinaccordancewith1-ES-1.2,andthereasonforthisresponse?A.ContinuetheRCScooldownwhilestoppingoneChargingPump;RCSsubcoolingis
adequatetopreventlossof
subcoolingmarginwhenoneChargingPumpis
stopped.B.OneChargingPumpmaybestoppedONLYIFatleastoneLowHeadSIpumpis
running;RCSsubcoolingisNOT
adequatetopreventlossof
subcoolingmarginwhenoneChargingPumpis
stopped.C.MaintainPZRlevelstableorincreasingwhilestoppingoneChargingPump;RCSsubcoolingis
adequatetopreventlossof
subcoolingmarginwhenoneChargingPumpis
stopped.D.ChargingPumps
mustremainrunningwithflowalignedtotheBIT;RCSsubcoolingisNOT
adequatetopreventlossof
subcoolingmarginwhenoneChargingPumpis
stopped.60
61.NorthAnnaPowerStation2008SROExamInitialConditions:*Unit1trippedfrom
100°1'<>powerduetoalossofallfeedflow.*MultiplefailurescausedalossofallAFW.Currentconditions:*ALLSG WideRangelevelsare
12°1'<>andslowlylowering.*RCSHotLeg
Temperaturesare560 0Fandslowlylowering.CoreExitTCsare565
0Fandslowlylowering.*LocalactionshaverestoredthecapabilitytofeedfromAFW.WhichONEofthefollowing
describesthemethodforrecoveryofHeatSinkinaccordancewith1-FR-H.1,LossofSecondaryHeatSink,andincludestheBasisforthatmethod?A.FeedonlyONESGat100gpm;Minimumflowtoensureadequateheatsink.B.FeedallthreeSGsat340gpmtotalflow;Minimumflowtoensureadequateheatsink.C.FeedallthreeSGsat340gpmtotalflow;
Ensure symetriccoolingduringNaturalCirculation.D.FeedonlyONESGat100gpm;Limitthermal
stressestoSGcomponents.
61
NorthAnnaPowerStation2008SROExam
62.Giventhe following:*Alossof off-site powerduetoa Tornadohittingthe
switchyard.*Thecrewhas
stabilizedtheUnitusing1-ES-O.1, Reactor Trip Response.*Operations
Management
has directed performanceofa Natural Circulation
Cooldown.WhichONEofthe following procedureswillbeusedto
performtheRCS Cooldown,andwhichONEofthe
followingisthe MAXIMUM cooldown rate allowable in accordancewiththeEOP
thatwillbeused?A.ES-O.2A, Natural Circulation
CooldownwithCRDMFans;15
degrees F/Hr.B.ES-O.2B, Natural Circulation
Cooldown withoutCRDMFans;25
degrees F/Hr.C.ES-O.2B, Natural Circulation
Cooldown withoutCRDMFans;15
degrees F/Hr.D.ES-O.2A, Natural Circulation
CooldownwithCRDMFans;25
degrees F/Hr.62
NorthAnnaPowerStation2008SROExam
63.Uponentryinto
1-ECA-2.1, Uncontrolled
DepressurizationofAllSteam
Generators, the crew determinesthatRCS cooldownrateis10goF/Hr.
WhichONE(1)ofthefollowingidentifies
the requirement
for controlling
AFWflowin accordance
with 1-ECA-2.1?A.Totalflowis
maintained>340gpmuntilANYSG
narrowrangelevelis
>110/0.B.Totalflowis
maintained>340gpmuntilALL8G
narrowrangelevelsare
>11%*C.Flowisreducedto100gpmtoeach8G,and
narrowrangelevelinALL
8G's iscontrolledatlessthan50%.D.Flowisreducedto100gpmtoeachSG,and
narrowrangelevelinALL
8G's iscontrolledat
greaterthan11%.63
NorthAnnaPowerStation2008SROExam
64.Giventhefollowing:*A small-breakLOCAoccurredonUnit1.Thecrew transitionsto1-E-1,Lossof
Reactor or Secondary Coolant.WhichONEofthefollowingwillFIRSTcauseanORANGEconditiononthe
Containment
CSF Status Tree?A.RecircSpray
sumplevelat4feet10inches.
B.Annunciator1J-A6,RXCONTSUMPHILEVEL,isLIT.
C.Containment
circularsumplevelindication
off-scale high.D.RecircSpraysumplevelat11feet10inches.
64
NorthAnnaPowerStation2008SROExam
65.ASmallBreakLOCAhasoccurredonUnit1.Thefollowingplant
conditions
exist: Complicationsinrecoveryhaveresultedinsomecore
damage.Containment
Pressurepeakedat22psiaandisslowly
decreasing.*Theteamhas
transitionedto1-FR-Z.3,ResponsetoHigh
ContainmentRadiationLevel.WhichONEofthefollowing
describesastrategyprovidedby1-FR-Z.3tomitigatethe
condition?A.Place Containment
AtmosphereFiltrationSysteminservice.B.StartOutsideRecircSpraypumpsandinjectingtheCAT.C.StartInsideRecircSpraypumpsandinjectingtheCAT.D.Vent ContainmentviatheIodineFilterbanks.
65
NorthAnnaPowerStation2008SROExam
66.In Emergency Operating Procedure 1-E-O, ReactorTripor Safety Injection, steps designatedwithan asterisk(*)nexttothestepare
_these steps applyfromthetimetheyare
encountered
until_A.Continuous
Action Steps;transitionfrom1-E-Ois
made B.Decision Making Steps;theEOP Networkisexited C.Decision Making Steps;transitionfrom1-E-Ois
made D.Continuous
Action Steps;theEOP Networkisexited 66
67.NorthAnnaPowerStation2008SROExamInaccordancewith
OP-AP-300, Reactivity
Management, reactorpowerisrequiredtobereducedbelow
100°A>PRIORtoperformingwhich
ONEofthefollowingevolutions?A.ReducingSteam
GeneratorBlowdownFlowRateB.Performingablended
makeuptotheRCSC.OperatingtheSteamDrivenAuxFeedPumpTurbineD.RaisingLetdown
temperature
67
NorthAnnaPowerStation2008SROExam68.Giventhefollowing:Unit1isshutdowninpreparationforRefuelinginaccordancewith
1-0P-4.1,ControllingprocedureforRefueling.Inaccordancewith
1-0P-4.1,whichONEofthefollowingchoices
describes(1)themethodoffillingtheRefuelingCavity
and(2)whichevolution
constitutestheFIRSTCoreAlteration?A.(1)GravityfillfromRWST,thenLHSIpump(2)LiftingoftheReactorVesselUpperInternalsB.(1)LHSIpumpONLY(2)LiftingoftheReactorVesselUpperInternalsC.(1)LHSIpumpONLY(2)ControlRodDriveShaftunlatchingD.(1)GravityfillfromRWST,thenLHSIpump(2)ControlRodDriveShaftunlatching
68
NorthAnnaPowerStation2008SROExam
69.Giventhe following:*An approach to criticalityisin progress in accordance
with 1-0P-1.5, Unit Startup from Mode3to Mode 2.*Source Range count rate priortothelastrod
withdrawal
was 4,000 CPS.*Source Range countrateisnow7,000CPSand
slowly increasing.
Source Range startuprateis+0.3OPMandstable.*Two minutes have elapsedsincethelastrod
withdrawal.
- Control Bank'C'isat110steps.
Which ONE of the following describe the sequence of actions required by 1-0P-1.5?A.Initiate
Boration at greaterthanorequalto10gpm,thentripthereactor.
B.Allow Source Range countrateto stabilize, then continue rod withdrawal.C.Insert Control Bank'0'to5steps,thentripthereactor.O.Initiate
Boration at greaterthanorequalto10gpm,then
insert Control Bank'0'to5 steps.69
NorthAnnaPowerStation2008SROExam
70.Giventhe following:*Unit1isat45%power.*Plant startupisin progress.*No other evolutionsarein progress WhichONEofthe following parametervaluesrequires
Technical Specification
actionwithinONE(1)hour?
A.Containment
air partial pressure12.9psia.B.Quadrant PowerTiltRatio1.022.C.RCS unidentified
leakageis1.20gpm.
D.RWST temperature
38 degrees F.70
NorthAnnaPowerStation2008SROExam
71.WhichONEofthefollowing
PeriodicTestsisdesignatedasan
Infrequently
Conducted or Complex Evolution?A.Rod operabilitytestingin accordancewith1-PT-17.1,ControlRodOperability.B.Turbine overspeedtriptestin
accordancewith1-PT-34.5, Turbine-GeneratorOverspeedTripTest.C.Turbinevalve
freedomtestin accordancewith1-PT-34.3, TurbineValveFreedom
Test.D.SolidState
ProtectionSystemtestingin
accordance
with 1-PT-36.1A,TrainAReactorProtectionandESFLogicActuationTest.
71
NorthAnnaPowerStation2008SROExam
72.Giventhefollowing:Unit1is defueledandthefuelassemblyinsertshuffleisinprogress.
- Annunciator1K-D3,RADMONITORSYSTEMFAILURETEST,actuates.Thenewfuelstoragearearadiationmonitorisnotedtobepeggedhighandunresponsivetosourcecheck.*Thefuelpitbridgeradiationmonitorindicationhasnotchanged.HealthPhysicsreportsradiationlevelsinthefuelbuildinghavenotchanged.WhichONEofthefollowingdescribestheFIRSTactionthatwillberequiredinaccordancewith
O-AP-5.1,CommonUnitRadiationMonitoringSystem?A.Verifythefuelbuildingventilationexhaustisalignedtothecharcoalfilter.B.Resetthenewfuelstoragearearadiationmonitorbypullingandreinsertingfuses.C.Placethefuelbuildingradiation
automaticinterlockkeyswitchinDISABLEwithintwominutes.D.Placethefuelbuildingradiation
automaticinterlockkeyswitchinENABLEwithintwominutes.
72
NorthAnnaPowerStation2008SROExam
73.WhichONEofthe following identifiesthe10CFR20
annual limit for TEDEandalso identifies
the EPIP 4.04 Emergency ExposureLimitfor saving valuable equipment?
A.5rem;25remB.3rem;10rem C.5rem;10remD.3rem;25rem 73
NorthAnnaPowerStation2008SROExam
74.Giventhefollowing:BothUnitsareat1
DD°A>power.*The followingalarmisreceivedonUnit2PanelF:*UNIT#1ANNSYS
POWER SUPPLY FAILURE*Thecrew enters1-AP-6,LossofMainControlRoom
Annunciators.WhichONEofthe
following describes requirements
in accordancewith1-AP-6iftheUnit1 Annunciatorsarenot immediately
restored?A.NOTrequiredtostationan
additional
operator to monitortheunit-1PCS;LogAFDevery3hours.B.Stationan
additional
operator to monitortheunit-1PCS;LogAFDeveryhour.C.NOTrequiredtostationan
additional
operator to monitortheunit-1PCS;LogAFDeveryhour.D.Stationan
additional
operator to monitortheunit-1PCS;LogAFDevery3hours.
74
NorthAnnaPowerStation2008SROExam
75.Giventhefollowing:Unit1isinMode5.*RCSDrainDowntoMidLoopisinprogressinpreparationforweldingonaHotLegopening.RHRPump1Aisinservice.*RHRPump1Bisavailable.Duringthedraindown,RHRampsanddischargepressurebeginfluctuating
erratically.
RCS temperaturehasrisenfrom121degreesFto127
degrees F.Thecrew enters1-AP-11,LossofRHR,andstopstheRCSdraindown.WhichONE(1)ofthefollowingdescribesthenextactionsthatwillberequiredinaccordancewith1-AP-11?A.ReduceRHRflowtominimumrequiredtomaintainRCS
temperatureand/orraiseRCSleveltoensureatleast10inchesabovetheHotLegcenterline.B.ReduceRHRflowtominimumrequiredtomaintainRCS
temperatureandmaximizeCCflowtoinserviceRHRheatexchangers.C.StopRHRPump1Aandinitiate
Attachment8,RefluxBoilingtocontrolRCS
temperature.D.StopRHRPump1Aand
immediatelystartRHRPump1B,thenverifythatRCStemperaturestabilizes.
75
76.NorthAnnaPowerStation2008SROExamInitialconditions:*Aspurious
TurbineRunbackoccurredonUnit1.*Tavewas5.5degreesFhigherthanTrefandrising.ControlBankDrodswereinsertingattherequiredrate.Currentconditions:*Reactorpower
580/0.*SteamDumpsclosed.*RodMotionstopped.*Taveand Tref are approximatelyequalandstable.*ControlBankDGroupStepcountersareat170steps.*AllControlBankDrodsindicate
approximately170steps,withtheexceptionofRodH-8,whichisat184steps.Ablownfuseisthecauseofthemispositionedrod.WhichONEofthefollowingidenifies(1)therodspeedofrodH-8PRIORtotheblownfuseand(2)
whetherornottheH-8controlrodisoperable?A.72SPM;H-8is
INOPERABLE.C.72SPM;H-8is
INOPERABLE.D.64SPM;H-8is
OPERABLE.76
NorthAnnaPowerStation2008SROExam
77.Giventhe following:Unit1isin Mode6with refuelingcavitylevelat289'10".
Upper internalshavebeenremoved.1ARHR pumpisin operationwith1BRHRpumpin
standby.*An electrical
faulton1Hbus causesalossofthebus.
WhichONEofthe following describestheactionrequired,andthebasisfortheaction
in accordance
with Technical Specifications?
A.Immediately
initiateactionto establish>/=23feetof water abovethetopofthe
reactor vessel flange;provides acceptableresultsin conjunction
with actions to initiate containmentclosuretolimit
radioactivereleasetothe
environment.
B.Immediately
suspendanyRCS makeup from sourceswithaboron
concentrationlessthanthatrequiredbyTS3.9.1;
ensuresthattherewillbeNORCS
makeup without adequate mixing.C.Immediately
initiateactionto establish>/=23feetof water abovethetopofthe
reactor vessel flange;abilityto remove decay heat and ensuremixingof borated RCS waterisdegraded.
D.Immediately
suspendanyRCS makeup from sourceswithaboron
concentrationlessthanthat
requiredbyTS3.9.1;
ensuresthatifRCSboron
concentrationisreducedduetoRCS
makeup, acceptable
margin for subcritical
operation is maintained.
77
NorthAnnaPowerStation2008SROExam
78.Giventhefollowing:*Unit1hasbeenat100
%powerfor12months.*Thefollowing
alarmsarereceived
approximately
5 minutes apart:*1J-D7, ACCUM 1A-1B-1CHI-LOLEVEL
1J-D8, ACCUM 1A-1B-1CHI-LOPRESS*SI Accumulatorlevelsand pressuresareasfollows:
1A 18 1C Level 67%72°Al 590/0 Pressure655psig670psig610psigGiventheselevelsand
pressureswhichONEofthe
following predictsthereasonforthealarmsAND
identifies
the status of accumulator
operability
in accordance
with Technical Specifications?A.Checkvalve
leakage is occurring;
SI accumulatorsareall operable.B.Vent valve leakage is occurring;oneSI accumulator
is inoperable.
C.Vent valve leakage is occurring;
SI accumulatorsareall operable.D.Checkvalve
leakage is occurring;oneSI accumulator
is inoperable.
78
NorthAnnaPowerStation2008SROExam
79.Thefollowing
conditions
exist:*Unit1isat100%power.*1-SI-P-1B,"B"LowHead
SafetyInjectionPumpistaggedoutfor
maintenance.*The1H Emergency Diesel Generator(EDG)is subsequently
determinedtobe inoperableduetothe discovery that non-qualifiedpartswereusedthelasttime
maintenance
was performedontheEDG.Basedonthese
plant conditions,whichONEofthefollowing
identifies
the equipmentthatmustbe
declared inoperableANDtherequiredactionin
accordance
with Technical Specifications?A.Declarethe1HEDGand1-SI-P-1A,"A"LowHead
SafetyInjectionPump
Verify correct breaker alignmentandindicated
power availabilityforeachrequiredoffsitecircuitwithin8hours.B.Declarethe1HEDG
1-SI-P-1A,"A"LowHead
SafetyInjectionPump
remains operable;Verify correct breaker alignmentandindicated
power availabilityforeachrequiredoffsitecircuitwithin1hour.
c.Declarethe1HEDGand
1-SI-P-1A,"A"LowHead
SafetyInjectionPump
Verify correct breaker alignment and indicated power availabilityforeachrequiredoffsitecircuitwithin1hour.D.Declare ONLYthe1HEDG inoperable;
1-SI-P-1A,"A"LowHead
Safety Injection Pump remains operable;Verify correct breaker alignment and indicated power availabilityforeachrequiredoffsitecircuitwithin8hours.
79
NorthAnnaPowerStation2008SROExam
80.Giventhe following:*BothUnits
were initially at 100 D A>powerwith1 J EDG OOS.*Operators began Unit 1 shutdownduetoa steam leak inside Containmentonthe BSG.*1-RC-PT-1444
failed high causing the associated
PORV, 1-RC-PCV-1455C
to open.*Attempts to close PORV 1-RC-PCV-1455Candthe associated
PORV Block Valve, 1-RC-MOV-1536
were unsuccessful
and operators trippedtheUnit.*The following occurred immediately
following the reactor trip:*BSG failed catastrophically
inside Containment
- Off-site power was lost*LowHeadSI
pump 1-SI-P-1A tripped on overcurrent
during startup.Power Supply estimates off-site power restorationin1.5to2hours.
WhichONEofthe following describes the procedure the operators will transition
to when leaving 1-E-0, ReactorTripor Safety Injection, AND how powerisrequiredtoberestoredto1
J Emergency Bus?A.1-E-1,Lossof
Reactor or Secondary Coolant;restore powerto1 J EmergencyBuswhen off-site power becomes available.B.1-E-1,Lossof
Reactor or Secondary Coolant;restore powerto1 J EmergencyBususingtheSBO
diesel.C.1-E-2, Faulted Steam Generator Isolation;
restore powerto1 J EmergencyBuswhen off-site power becomes available.D.1-E-2, Faulted Steam Generator Isolation;
restore powerto1 J EmergencyBususingtheSBO
diesel.80
NorthAnnaPowerStation2008SROExam
81.Unit1isat100%power.1K-G1,SFGDSPROTSYSTRATROUBLEhasbeenalarmingintermittently.
Instrument
Department
has determineda48VDCpowersupplyinTrainAisdegradingandwillmostlikelyfail
completelyinthenearfuture.WhichONEofthefollowing
describesthecorrectresponse?
Reference ProvidedA.Online replacementofthepowersupplyispermitted;followingpowersupply
replacementtheReactorTripBypassBreakermaybeclosedforupto2hourstoperform1-PT-36.1A,TrainAReactorProtectionandESFLogic ActuationLogicTest.B.Online replacementofthepowersupplyisNOTpermitted;beinHotStandbywithin30hours.C.Online replacementofthepowersupplyisNOTpermitted;beinHotStandbywithin48hours.D.Online replacementofthepowersupplyispermitted;followingpowersupply
replacementtheReactorTripBypassBreakermaybeclosedforupto4hourstoperform1-PT-36.1A,TrainA
ReactorProtectionandESFLogic ActuationLogicTest.
81
NorthAnnaPowerStation2008SROExam
82.Giventhe following:*A LOCAisin progressonUnit1.*AllRCPsare
stopped.*RVLISFull
Range isCoreExitTCsare
reading 1250 degrees F.*ALLSGNR levels are OFF-SCALE low.*NO source ofSGfeedhasbeen
established.
NO source of ECCShasbeen established.*The crew has attempted secondary depressurization
in accordancewithFR-C.1, Response to InadequateCoreCooling,butthe
attempt was ineffective.Giventhese
plant conditions,whichONEofthe
following identifies
the procedureactionto mitigate this event?A.Immediately
transition
to SACRG-1, Severe Accident Control Room Guideline Initial Response, BEFORE opening PZR PORVs and Block Valves, and other RCS Vent Paths.B.Remainin
FR-C.1,openPZR PORVs and Block Valves, and other RCS Vent Paths.C.OpenPZR PORVs and Block Valves, and other RCS Vent PathsandTHEN transition
to SACRG-1, Severe Accident Control Room Guideline Initial Response.D.Remainin
FR-C.1, startoneRCPinanidleloop.
82
NorthAnnaPowerStation2008SROExam
83.Giventhe following:Unit1isin Mode5withRCS draindown in progress.*The crew observes1BRHR Pump dischargeflowand motor amps oscillating.
The crew isolatesknownRCSdrainpathsand
maximizes Charging flow.RCSlevel continues to decrease.*AnnunciatorE-A8,RHR SYSTEM LaFLOW,is alarming intermittently.
Containment
sump pumpsarerunning
continuously.*An operator leaving Containment
reports leakage observedfromthePZRSurge
Line.WhichONEofthe following describes the procedural
guidance that will mitigate these plant conditions?
A.Perform 1-AP-17, Shutdown LOCA;initiate Attachment8,HotLeg Injection.B.Perform 1-AP-11, Loss of RHR, Attachment
2, MinimumRCSLevelforIndicated
Flow.C.Perform 1-AP-17, Shutdown LOCA, Attachment7,ColdLeg Injection.D.Perform 1-AP-11,LossofRHR, Attachment
3, Determining
AcceptableRHRFlow Reductions.
83
84.NorthAnnaPowerStation2008SROExam*Unit1isat
1000/0power.Unit2isinMode5.Unit1and2CCsystemsaresplit.*TheOATCreportsthefollowingalarmsandindications:*1G-E8, CaMPCOOLPP1BAUTOTRIP*1G-B3,CCHX1A-1BCCOUTLET
La FLOW1G-C3,CCHX
OUTLET La PRESS1C-C4,RCP1A-B-CCCTHERMBARR
HI/La FLOW*1A-E6,RCP1B
VIBRATION ALERT/DANGER
RCP ThermalBarrierHeatExchangerflow
indicatorsallread0GPM.*RCPMotorBearing
temperaturesare146°Fandrisingat5°Fperminute.*1BRCP Vibration readings:*2-3mils Seismic8-10milsProximityGiventheseplantconditions,whichONEofthefollowing
identifiestherequiredprocedureANDalso
identifiestheDesignBasisoftheCCSysteminaccordancewiththeTechnical
Specification
Bases?A.1-AP-15,Lossof
Component Cooling;TWOCC Subsystems
are sufficienttoaccomplishafastcooldownofoneunitwhilemaintainingnormalloadsontheotherunit.
B.1-E-0,ReactorTriporSafetyInjection;THREECC Subsystems
are sufficienttoaccomplishafastcooldownofoneunit
while maintainingnormalloadsontheotherunit.C.1-AP-15,Lossof
Component Cooling;THREECC Subsystems
are sufficienttoaccomplishafastcooldownofoneunit
while maintainingnormalloadsontheotherunit.D.1-E-0,ReactorTriporSafetyInjection;TWOCC Subsystems
are sufficienttoaccomplishafastcooldownofoneunitwhilemaintainingnormalloadsontheotherunit.
84
NorthAnnaPowerStation2008SROExam
85.Giventhe following:Unit1isin Mode 3 during a plant cooldown.Chemistry sampleofthe Quench Spray System Chemical Addition Tank determines
that NaOH concentrationis1 0%by weight.Chemical Addition Tank contains approximately
5510 gallons.*1-QS-P-1B, Quench SprayPump1B,isoutof
service.WhichONEofthe following describeshowthe current status of the Quench Spray/Chemical
Addition Tank affects the plant during a Design Basis LOCA in accordancewiththe Technical Specification
Bases?A.Chemical Addition Tank NaOH concentration
(10%by weight)is outsideoflimits which affectsthepHofthe
resultant Containment
sump water solutionandthe ability to effectively
remove Iodine following a DBA LOCA.B.Chemical Addition Tank volume (5510 gallons)is outside of limits which affects the ability to maintain Containment
within design pressure limits and affectstheability
to maintain Iodine at acceptable
levels following a DBA LOCA.C.Inoperability
of 1-QS-P-1Bwill resultina Containment
peak temperature
higherthanthe value calculatedinthe accident analysis for a DBA LOCA.D.Inoperability
of 1-QS-P-1Bwill resultina Containment
peak pressure higher than the value calculatedinthe accident analysisfora DBA LOCA.85
NorthAnnaPowerStation2008SROExam
86.Giventhe following:*Unit1core
off-load in progress.*The3 most recently off-loaded
irradiated
fuel assemblies
are storedasfollows:
Assembly(En
rich ment)Assembly A (4.6%)Assembly B (3.20/0)Assembly C (3.2%)Burnup 30,000 MWD/MTU 30,000 MWD/MTU 20,000 MWD/MTU Location Non-Matrix
location Low-Reactivity
5X5 matrix Low Reactivity
5X5 matrix WhichONEofthe following identifies
the minimum required action in accordance
with Technical Specification 3.7.18, SpentFuelPool StorageANDthe Basesfortheaction?ReferenceProvided
A.ONLYONEfuel assemblyisrequiredtobemoved;
ensures that Keff will remain<0.95forall
postulated
accidents assumingthatthe solubleboroninthe
SpentFuelPoolisattheTS
3.7.17, Fuel StoragePoolBoron Concentration, minimum limit.B.TWO fuel assemblies
are requiredtobemoved;
ensures that Keff will remain<0.95forall
postulated
accidents assumingthatthe solubleboroninthe
SpentFuelPoolisattheTS3.7.17,Fuel
StoragePoolBoron Concentration, minimum limit.C.TWO fuel assembly are requiredtobemoved;
ensures that Keff will remain<0.95forall
postulated
accidents assuming NO solubleboroninthe
SpentFuelPool.D.ONLYONEfuel assembly is requiredtobemoved;
ensures that Keff will remain<0.95forall postulated
accidents assuming NO solubleboroninthe
SpentFuelPool.86
87.NorthAnnaPowerStation2008SROExam*Unit1has experienced
a Steam Generator Tube Rupture.*The crew is performing
1-ES-3.1, Post-SGTR Cooldown Using Backfill.CoreExitTCsare
345°FRCSHotLeg Temperatures
are 335°F RCS Wide Range Pressureis600psig1CRCPis runningandthe crew has commenced depressurizingtheRCS.Giventhe above plant conditions,whichONEofthe
following identifies
the parameterthatwill determine when the depressurizationwillbe stopped,ANDalso provides theBasisfor controllingtherateof depressurization?A.RCP number1seal differential
pressure;controlthe
depressurizationrateto ensure pressure controlisnotlost.B.RCS Subcooling
basedonCoreExitTCs;controlthe
depressurizationrateto ensure pressure controlisnotlost.C.RCS Subcooling
basedonCoreExitTCs;controlthe
depressurizationrateto minimize head voiding.D.RCP number1seal differential
pressure;controlthe
depressurizationrateto minimize head voiding.87
NorthAnnaPowerStation2008SROExam
88.Giventhefollowing:Unit1isat100%power.Thefollowingalarmisreceived:*1B-A5,CWPP
1A-1B-1C-1DAUTO
TRIP*CWPump1B motorindicates0ampsCWPumps1A,1C,and
10motorsindicate300-310amps.
Condenserpressureis3inchesHgabsoluteand
degrading slowly.WhichONEofthefollowing
describesthemitigationstrategyfortheeventinprogress?A.Perform1-AP-13,LossofOneorMoreCirculating
WaterPumps;reduceCWPumpampstoprevent
motor damage.Perform1-AP-14,Low
CondenserVacuum;guidanceforestimatingRCSborationflowratesduringaloadreductionisNOTprovidedin1-AP-14.B.Perform1-AP-13,LossofOneorMoreCirculating
WaterPumps;contactHPtodetermineifliquidwastereleasemustbesecured.Perform1-AP-14,Low
CondenserVacuum;guidancefor
estimatingRCSborationflowratesduringaloadreductionisNOTprovidedin1-AP-14.C.Perform1-AP-13,LossofOneorMoreCirculating
WaterPumps;contactHPtodetermineifliquidwastereleasemustbesecured.Perform1-AP-14,Low
CondenserVacuum;guidancefor
estimatingRCSborationflowratesduringaloadreductionisprovidedin1-AP-14.D.Perform1-AP-13,LossofOneorMoreCirculating
WaterPumps;reduceCWPumpampstoprevent
motor damage.Perform1-AP-14,Low
CondenserVacuum;guidancefor
estimatingRCSborationflowratesduringaloadreductionisprovidedin1-AP-14.
88
NorthAnnaPowerStation2008SROExam
89.Giventhefollowing:*Unit1isat100
%power.*120VACVitalBus
Inverter 1-11failed8hoursago.*120VACVitalBus
1-11isbeingpoweredfromits
associated
constant voltage source transformer.WhichONEofthe
following identifies
the minimum Technical SpecificationLCOsthatcontainrequired
actionsfortheseplant
conditions,includingtherequired
compensatory
measures in accordancewiththe Technical Specification
Bases?Reference ProvidedA.TS3.8.7, Inverters-Operating,LimitingActionisrequiredtobeentered;TS3.8.9, Distribution
Systems-Operating,LimitingActionisNOTrequiredtobe
entered;Concurrent
planned EDG maintenanceisNOTallowed.B.BOTHTS3.8.9, Distribution
Systems-OperatingANDTS3.8.7,InvertersOperatingLimiting
Actionsarerequiredtobeentered;
Concurrent
planned EDG maintenanceisNOTallowed.C.TS3.8.9, Distribution
Systems-Operating,LimitingActionisrequiredtobe
entered;TS3.8.7, Inverters-Operating,LimitingActionisNOTrequiredtobeentered;
Concurrent
planned EDG maintenancecanbe performed.D.BOTHTS3.8.9, Distribution
Systems-OperatingANDTS3.8.7,Inverters
Operating Limiting Actionsarerequiredtobeentered;
Concurrent
planned EDG maintenancecanbe performed.
89
NorthAnnaPowerStation2008SROExam
90.Giventhefollowing:
1-FR-H.1, ResponsetoLossofSecondaryHeatSink,isinprogress.*AttemptstoestablishAuxFeedwaterfloware
unsuccessful.RCSBleedandFeedhasNOTbeeninitiated.*Main FeedwaterflowhasjustbeenestablishedandSGlevelsareasfollows:'1A'40%widerangeandrising
- '1B'40%widerangeandstable
- '1C'29%widerangeandloweringCoreexit Tesarestable.
- Containmentpressureis19.2psia.WhichONE(1)ofthefollowingdescribestheappropriate
operator action?A.Returnto
procedureandstepineffectandcontinue
effortstoestablish
AFW flow.B.PerformSteps14through23of1-FR-H.1toinitiateRCSbleedandfeed.C.Remainin1-FR-H.1untilCoreExitTCsindicatea
decreasing
trend.D.Remainin1-FR-H.1untilallSGwiderangelevelsindicateanincreasingtrend.
90
NorthAnnaPowerStation2008SROExam
91.Giventhefollowing:TheUnitisinMode6.RodUnlatchingisinprogress.
ManipulatorCraneradiationmonitor,1-RM-RMS-162, suddenlypegshigh.Thefollowingalarmsarereceived:*1K-D2,RAD
MONITORSYSTEMHIRADLEVEL*1K-D3,RAD
MONITORSYSTEMHI-HIRADLEVELHPhas confirmedthatradiationlevelsontherefuelingdeckarenormalandOperationshasdeclared
1-RM-RMS-162
inoperable.WhichONEofthefollowing
describestherequiredactionsin
accordancewith1-AP-5,Unit1Radiation
Monitoring
System?A.VerifyControlRoomBottledAirdump;
Core alterations
may continue with 1-RM-RMS-162
Continuous
HPcoverageisrequired.B.Verify Containment
Ventilation
Isolation;
Core alterationsmayNOT continue with 1-RM-RMS-162
inoperable.C.VerifyControlRoomBottledAirdump;
Core alterationsmayNOT continue with 1-RM-RMS-162
inoperable.D.Verify Containment
Ventilation
Isolation;
Core alterations
may continue with 1-RM-RMS-162inoperable.Continuous
HPcoverageisrequired.
91
NorthAnnaPowerStation2008SROExam
92.Giventhe following:*Bothunitsareat100
%power.*1-SW-P-1A and 1-SW-P-1Barerunning.
- 2-SW-P-1BisOOS.1-SW-P-1Btripsand 2-SW-P-1Aisstarted.
Which ONE of the following describes the Technical Specificationactionrequired,andtheBasesforthe
action?A.Restore the Service WaterLoopto operable status within72hours;Ensures design flowstotheRSHeat
Exchangers
are achieved followingaLOCAwithONE additional
failure.B.Throttle Service WatertoCC Heat Exchangers
within1hour;Ensures design flowstotheRSHeat
Exchangers
are achieved followingaLOCA with-NO additional
failures.C.Restore the Service WaterLoopto operable status within72hours;Ensures design flowstotheRSHeat
Exchangers
are achieved followingaLOCAwithNO additional
failures.D.Throttle Service WatertoCC Heat Exchangers
within1hour;Ensures design flowstotheRS Heat Exchangers
are achieved followingaLOCAwithONE additional
failure.92
NorthAnnaPowerStation2008SROExam
93.Giventhe following:*A reactortriphas occurredonUnit1.*Following transition
to 1-ES-0.1, Reactor Trip Response, the STAreportsall
CSF status trees GREENwiththe EXCEPTION of HeatSink,whichis
YELLOW.*The following SG conditions
are observed:*ASG pressure1050psigandstable.*ASGlevel 25%NRandrising.*BSG pressure1150psigandstable.*BSGlevel92%NRandrising.*CSG pressure1050psigandstable.CSGlevel 20%NRandrising.*B MSIV indicates CLOSED.*AFWflowis160GPMtoeachSG.*Thecrew determines
thatentrytoa Yellow Path procedurewillhelp mitigate the event.WhichONEofthe following describes the mitigation
strategyusedtorestoretheHeat
Sink Critical Safety Function to GREEN?A.Perform 1-FR-H.3, Response to Steam GeneratorHighLevel;
isolate AFWflowto B SG.Initiate blowdown from BSGandDO NOT dump steam from B SG.B.Perform 1-FR-H.2, Response to Steam Generator Overpressure;
Isolate AFW flow to BSGanddonot
restore AFWflowuntila
steam releasepathis established.
C.Perform 1-FR-H.2, Response to Steam Generator Overpressure;
Verify Main Feedwater Isolation.
Dump steam from BSGto reduceHotLeg temperatures.
D.Perform 1-FR-H.3, Response to Steam GeneratorHighLevel;
Verify Main Feedwater Isolation.
Dump steam from BSGto reduceHotLeg temperatures
and initiate blowdownfromBSG.93
NorthAnnaPowerStation2008SROExam
94.Giventhefollowing:*Thedateis6/5/2008.*BothUnitsareinMode1.*Shift complementisatMINIMUMallowedbyTechnical
Specifications.*Oneofthe ReactorOperatorsbecomesillandmustbe
transportedtothe hospital.*TWOpotential
replacementsareidentifiedforcall-in.*BOTH replacementshavebeenassignedtoOPS
Supportforthelastyear.Thelasttimestheywereonshiftareasfollows:OperatorA*12hoursonMarch24BOP*12hoursonFebruary23BOP*12hoursonFebruary22BOP
- 12hoursonJanuary19BOP*12hoursonJanuary18BOP
Operator B12hoursonMarch21RO12hoursonMarch20RO12hoursonMarch19RO12hoursonMarch18RO12hourson January5WCCWhichONEofthefollowingidentifiestheTechnical
Specification
requirement
toreplacethe
ReactorOperator,andwhich
operatorwillbeselectedasthereplacement?A.ActionmustbetakentoensuretheReactorOperatorisreplacedwithin2hours;OperatorBwillbeselected.B.ActionmustbetakentoensuretheReactorOperatorisreplacedwithin2hours;OperatorAwillbeselected.C.ActionmustbetakentoensuretheReactorOperatorisreplacedwithin1hour;OperatorBwillbeselected.D.ActionmustbetakentoensuretheReactorOperatorisreplacedwithin1hour;OperatorAwillbeselected.
94
NorthAnnaPowerStation2008SROExam
95.Giventhe following:*The Shift Managerisinthecontrolroom
discussing
an upcomingevolutionwiththeUnit2Unit
Supervisor.*TheUnit1Unit
Supervisorisonaplant
walkdownwhenthefollowingevents
occur:Unit1 experienced
a spuriousTurbinerunback.
- While stabilizingtheunitat 65%power,a turbinetripoccurred.TheUnit1 reactordidNOTtrip,either
automatically
or manuallyfromthecontrolroom.PZRPORV, 1-RC-PCV-1455C,isstuckOPEN.*The associatedblockvalve, 1-RC-MOV-1536,didNOTclosewhentheOATCtookthecontrolswitchtoclose.
Safety Injectionisactuated.TheUnit1Unit
Supervisorwasinjuredwhile
returningtothecontrolroom
and needs medical assistanceinthe Turbine Building.In accordance
with DNAP-0509, Dominion Nuclear Procedure AdherenceandUsage,whichONEofthe
following identifieswhowillbetheEOP
'Reader,'ANDalsoidentifiestherequiredEOP
flowpathuponexiting1-FR-S.1, Response to Nuclear Power Generation/ATWS?A.Unit 2 Unit Supervisor;Goto1-E-1,Loss
of Reactor or Secondary Coolant.B.Unit 2 Unit Supervisor;Returnto 1-E-O, ReactorTriporSafetyInjection.C.ShiftManager;Goto1-E-1,Lossof
Reactor or Secondary Coolant.D.ShiftManager;Returnto 1-E-O, ReactorTriporSafetyInjection.
95
NorthAnnaPowerStation2008SROExam
96.Giventhefollowing:*Unit1is operatingat100%power.*Thefollowingalarmisreceivedseveraltimesina10
minute period:1D-H5,HIGH
CAPACITY S/G BLOWDOWN TROUBLE Local indicationattheHigh CapacityS/GBlowdownControlPanelisnormal.*The Instrument
Technician
investigatingthealarm determinesthatthe comparatorcardforthe
annunciatorisfailing.*A replacement
comparatorcardis unavailable
and assistancehasbeenrequestedfrom
Engineering.*Torestore
functionalityofthealarmintheinterima
jumper mustbeinstalled.
WhichONEofthe following procedureswillgovernthe
installationofthe jumper, andwho,bytitle,mustprovide
FINAL approvalofthe jumper?A.OP-NA-200-1001, Equipment ClearanceProcess;FSRC (formerlyknownas SNSOC).B.VPAP-1403, Temporary Modifications;ShiftManager.C.OP-NA-200-1001, Equipment Clearance Process;Shift Manager.D.VPAP-1403, Temporary Modifications;
FSRC (formerlyknownasSNSOC).
96
NorthAnnaPowerStation2008SROExam
97.Given the following:*A Unit 1 RCS heatupisin progress.*RCS Tave is 342°F.1H Emergency Diesel Generator is declared INOPERABLE
due to failure of the Shutdown Relay.curren t Which ONE of the following identifies
(1)thefOPERATIONAL
MODE and(2)the Technical Specification
requirements
to enter the next higher Mode?A.(1)(2)B.(1)(2).C.(1)(2)D.(1)(2)Mode 3 Change to Mode 2 may be performed providedtheTS 3.8.1, AC SourcesOperating, Action Statements
for1H EDG inoperability
are satisfied.
Risk evaluation
and NRC approval is NOT required.Mode 4 Change to Mode 3 may be NOT performed withoutarisk evaluation
and approval from the NRC.Mode 3 Change to Mode 2 may be NOT performed withoutarisk evaluation
and approval from the NRC.Mode 4 Change to Mode 3 may be performed provided the TS 3.8.1, AC SourcesOperating, Action Statements
for1H EDG inoperability
are satisfied.
Risk evaluation
and NRC approval is NOT required.97
NorthAnnaPowerStation2008SROExam
98.WhichONEofthe following describes the Release Permit approval process in accordance
with 0-OP-23.3, Waste Gas Decay Tanks&Waste Gas Diaphram Compressors, AND also identifies
the Technical Specification
Bases for the maximum radioactivity
content in each gas storage tank?A.Operations
initiates the release request and Health Physics (HP)authorizes
the release permit;an individualatthe exclusion boundarywillnot exceed0.5remtotal
body exposureinthe event of an uncontrolled
releaseofa tanks contents.B.Chemistryinitiates
the release request and Health Physics (HP)authorizes
the release permit;an individualatthe exclusion boundarywillnot exceed0.5rem total body exposureinthe event of an uncontrolled
releaseofa tanks contents.C.Chemistryinitiates
the release request and Health Physics (HP)authorizes
the release permit;an individualatthe exclusion boundarywillnot exceed0.1remtotal
body exposureinthe eventofan uncontrolled
releaseofa tanks contents.D.Operations
initiates the release request and Health Physics (HP)authorizes
the release permit;an individualatthe exclusion boundarywillnot exceed0.1remtotal
body exposureinthe event of an uncontrolled
releaseofa tanks contents.98
99.NorthAnnaPowerStation2008SROExam
Initial conditions:
- Unit1isin Mode 3 shuttingdownfora scheduled refueling.*Afireisin
progressinthe Motor Driven AFW Pump House.TheFire Brigadeisatthescene.
Current conditions:*Thefirewas
burning for 12 minutesandisnow extinguished.*The1B MDAFW Pump motor was destroyedbythefire.
Which ONE of the following describes the impact on Safe Shutdown Functions, and whether E-Plan action is required in accordance
with O-FCA-O, Fire ProtectionOperations
Response?A.The Reactor Heat Removal function requiredtogetfrom Mode4to Mode5is affected;EPIP1.01, Emergency Manager Controlling
Procedure is NOT requiredtobe implemented.B.The Reactor Heat Removal function requiredtogetto Mode4is affected;EPIP1.01, Emergency Manager Controlling
Procedure is requiredtobe implemented.C.The Reactor Heat Removal function requiredtogetto Mode4is affected;EPIP1.01, Emergency Manager Controlling
Procedure is NOT requiredtobe implemented.D.The Reactor Heat Removal function requiredtogetfrom Mode4to Mode5is affected;EPIP1.01, Emergency Manager Controlling
Procedure is requiredtobe implemented.
99
100.NorthAnnaPowerStation2008SROExam*ALOCAhasoccurredonUnit1.*RCSpressureindicates190psigandstable.*RCS temperatureis260degreesFandlowering.
Containmentpressureis27psia.LowHeadSIflowindicates1200gpmoneachtrain.*All equipmentisoperatingasdesigned.*Thecrewhas
justentered1-ES-1.3, TransfertoColdLegRecirculation.*TheSTAreportsaREDpathonthe
INTEGRITYCSFStatusTree.Giventheseplantconditions,whichONEofthefollowing
describesthehierarchyofrequriedprocedureactions?A.Remainin1-ES-1.3until
transfertoColdLegRecirculationiscompletethroughstep8;Transitionto1-FR-P.1andverifythatRCSpressureisbelowtheLowHeadSI
pump shutoffhead,thenreturnto1-ES-1.3.B.Remainin
1-ES-1.3 until transfertoColdLegRecirculationiscompletethroughstep8;Transitionto1-FR-P.1andperformtheactionstostoptheRCScooldown,thenreturnto1-ES-1.3.C.Immediately
transitionto1-FR-P.1,Responseto
ImminentPressurizedThermal
Shock;VerifythatRCS
pressureisbelowtheLowHeadSIpump
shutoffheadandthenreturnto1-ES-1.3.D.Immediately
transitionto1-FR-P.1,Responseto
ImminentPressurizedThermal
Shock;Performtheactionsof1-FR-P.1tostoptheRCScooldownandthenreturnto
1-ES-1.3.100
RTS Instrumentation
3.3.1 3.3 INSTRUMENTATION
3.3.1ReactorTrip
System (RTS)Instrumentation
LCO 3.3.1 The RTS instrumentationforeachFunctioninTable
3.3.1-1 shall be OPERABLE.APPLICABILITY:
AccordingtoTable 3.3.1-1.ACTIONS----------------
NOTE---------------SeparateCondition
entry isallowedforeachFunction.
CONDITION REQUIRED ACTION COMPLETION
TIME A.One or more Functions A.1EntertheCondition
Immediately
with one or more referenced
in requiredchannelsor
Table 3.3.1-1 for the trains inoperable.
channel(s)or train(s).B.One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Trip channel OPERABLE status.inoperable.
OR-B.2 Be in MODE 3.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> C.One channel or train C.1 Restore channel or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable.
train to OPERABLE status.OR-C.2.1 Initiate action to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> fully insert all rods.AND (continued)
-North AnnaUnits1 and 2 3.3.1-1 Amendment 231/212
ACTIONS RTS Instrumentation
3.3.1 CONDITION C.(conti nued)D.One Power Range Neutron Flux-High channel inoperable.
REQUIRED ACTIONC.2.2Placethe
Rod Control Systemina conditionincapableofrod
withdrawal.
NOTE-------------
The inoperable
channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance
testing and setpointadjustmentof
other channels.COMPLETION
TIME 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> 0.1.1 Place channel in trip.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 0.1.2 Reduce THERMAL POWER to75%RTP.OR 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> 0.2.1 Place channel in trip.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND-------------NOTE-----------
Only requiredtobe performed when the Power Range NeutronFluxinputto
QPTR is inoperable.
0.2.2 Perform SR 3.2.4.2.OR 0.3 Be in MODE 3.North AnnaUnits1 and 2 3.3.1-2 Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 78 hours Amendment 231/212
ACTIONS RTS Instrumentation
3.3.1 CONDITION REQUIRED ACTION COMPLETION
TIME E.One channel------------NOTE-------------
The inoperable
channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance
testing of other channels.-----------------------------E.1Place channel in trip.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR-E.2 Be in MODE 3.78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> F.One Intermediate
Range F.1 Reduce THERMAL POWER 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Neutron Flux channel to<P-6.inoperable.
OR-F.2 Increase THERMAL POWER 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to>P-10.G.Two Intermediate
Range------------NOTE-------------
NeutronFluxchannelsLimited
plant cool down or inoperable.
boron dilution is allowedprovidedthe
change is accountedforinthe calculated
SDM.-----------------------------
G.1 Suspend operations
Immediately
involving positive reactivity
additions.
AND-G.2 Reduce THERMAL POWER2hours to<P-6.North AnnaUnits1 and 2 3.3.1-3 Amendment 231/212
ACTIONS RTS Instrumentation
3.3.1 CONDITION REQUIRED ACTION COMPLETION
TIME H.One Source Range------------NOTE-------------
Neutron Flux channel Limited plant cool down or inoperable.
boron dilution is allowedprovidedthe
change isaccountedforinthe
calculated
SDM.-----------------------------
H.1 Suspend operations
Immediately
involving positive reactivity
additions.I.Two Source RangeI.1 OpenReactorTrip
Immediately
NeutronFluxchannels
Breakers (RTBs).inoperable.
J.One Source Range J.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Neutron Flux channel OPERABLE status.inoperable.
OR-J.2.1 Initiate action to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> fully insert all rods.AND-J.2.2Placethe Rod Control 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> Systemina condition incapableofrod withdrawal.
North AnnaUnits1 and 2 3.3.1-4 Amendment 231/212
ACTIONS RTS Instrumentation
3.3.1 CONDITION REQUIRED ACTION COMPLETION
TIME K.RequiredSource
Range------------NOTE-------------
Neutron Flux channel Plant temperature
changes are inoperable.allowedprovidedthe
temperature
change isaccountedforinthe
calculated
SDM.-----------------------------
K.l Suspend operations
Immediately
involving positive reactivity
additions.
AND-K.2 Perform SR 3.1.1.1.1hour AND-Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter
L.One channel------------NOTE-------------
The inoperable
channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance
testing of other channels.-----------------------------
L.l Place channel in trip.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR-L.2 Reduce THERMAL POWER 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> to<P-7.North AnnaUnits1 and 2 3.3.1-5 Amendment 231/212
ACTIONS RTS Instrumentation
3.3.1 CONDITION M.OneReactorCoolant
Pump Breaker Position channel inoperable.
REQUIRED ACTION------------NOTE-------------
The inoperable
channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance
testing of other channels.COMPLETION
TIME M.l OR M.2 Restore channel to OPERABLE status.Reduce THERMAL POWER to<P-7.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours N.OneTurbineTrip
channel inoperable.
NOTE-------------
The inoperable
channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance
testing of other channels.N.lPlace channel in trip.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR N.2 Reduce THERMAL POWER to<P-8.76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> O.One train inoperable.
NOTE-------------
One train may be bypassed for up to 4hoursfor surveillance
testing provided the other train is OPERABLE.0.1 OR Restore train to OPERABLE status.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.2 Be in MODE 3.North Anna Units 1 and 2 3.3.1-6 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> Amendment 231/212
ACTIONS RTS Instrumentation
3.3.1 CONDITION REQUIRED ACTION COMPLETION
TIME P.One RTB train------------NOTES------------
1.One train maybebypassed
for upto2hours for surveillance
testing,providedthe
other train is OPERABLE.2.One RTB maybebypassed
for upto2hours for maintenance
onundervoltageorshunt
trip mechanisms,providedthe
other train is OPERABLE.3.One RTB train may be bypassed for upto4hours for concurrent
surveillance
testing of the RTB and automatic trip logic,providedthe
other train is OPERABLE.-----------------------------
P.1 Restore trainto1hour OPERABLE status.OR-P.2 Be in MODE 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Q.One or more channels Q.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable.
required state for existing unit conditions.
OR-Q.2 Be in MODE 3.7hours North AnnaUnits1 and 2 3.3.1-7 Amendment 231/212
RTS Instrumentation
3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION
TIME R.One or more channelsR.lVerify interlock isin1hour inoperable.
required state for existing unit conditions.
OR-R.2 Be in MODE 2.7hours S.One trip mechanismS.1Restore
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable
for one trip mechanism to RTB.OPERABLE status.OR-S.2 Be in MODE 3.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> SURVEILLANCE
REQUIREMENTS----------------
NOTE---------------RefertoTable
3.3.1-1todetermine
which SRs apply for each RTS Function.SR 3.3.1.1 SR 3.3.1.2 SURVEILLANCE
Perform CHANNEL CHECK.-------------------NOTE--------------------
Not requiredtobe performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER is15%RTP.FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Compare results of calorimetric
heat 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> balance calculation
to power range channel output.Adjust powerrangeoutput
if calorimetricheatbalance
calculation
result exceeds power range channel output by more than+2%RTP.North AnnaUnits1 and 2 3.3.1-8 Amendment 231/212
SURVEILLANCE
REQUIREMENTS
SURVEILLANCE
RTS Instrumentation
3.3.1 FREQUENCY SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7-------------------NOTE--------------------
Not requiredtobe performed until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after THERMAL POWER is15%RTP.Compare resultsoftheincore
detector measurementstoNuclear Instrumentation
System (NIS)AFD.Adjust NIS channel if absolute difference
is3%.-------------------NOTE--------------------
This Surveillance
must be performed on the reactor trip bypassbreakerimmediately
after placing the bypassbreakerin service.Perform TADOT.Perform ACTUATION LOGIC TEST.-------------------NOTE--------------------
Verification
of setpoint is not required.Perform TADOT.-------------------NOTE-------------------
Not required to be performedforsource range instrumentation
prior to entering MODE 3 from MODE 2 until4hours after entry into MODE 3.Perform COT.31 effective full power days (EFPD)31 days on a STAGGERED TEST BASIS 31 days on a STAGGERED TEST BASIS 92 days 92 days North AnnaUnits1 and 2 3.3.1-9 Amendment 231/212
RTS Instrumentation
3.3.1 SURVEILLANCE
REQUIREMENTS
SR 3.3.1.8 SURVEILLANCE
NOTE--------------------
This Surveillance
shall include verification
that interlocks
P-6 and P-I0arein their required state for existing unit conditions.
FREQUENCY
Only required when not performed within previous 92 days SR 3.3.1.9 Perform COT.Priorto reactor startup ANDFourhours after reducing power belowP-6forsourcerange
instrumentation
AND Twelve hours after reducing power below P-I0 for power and intermediate
range instrumentation
AND Once per 92 days thereafter
NOTES-------------------1.Adjust NIS channel if absolute difference3%.2.Not requiredtobe performed until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after THERMAL POWER is50%RTP.Compare resultsoftheexcorechannelsto
incore detector measurements.
92 EFPD North AnnaUnits1 and 2 3.3.1-10 Amendment 231/212
SURVEILLANCE
REQUIREMENTS
SURVEILLANCE
SR 3.3.1.10
This Surveillance
shall include verification
thatthetime constants are adjustedtothe prescribed
values.Perform CHANNEL CALIBRATION.
SR 3.3.1.11
Neutron detectorsareexcluded
from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION.
SR 3.3.1.12 Perform CHANNEL CALIBRATION.
SR 3.3.1.13 Perform COT.RTS Instrumentation
3.3.1 FREQUENCY 18 months 18 months 18 months 18 months SR 3.3.1.14
Verification
of setpointisnot required.Perform TADOT.SR 3.3.1.15
Verification
of setpointisnot required.Perform TADOT.18 months Prior to exceeding the P-8 interlock whenever the unit has been in MODE3,ifnot performed withintheprevious
31 days North AnnaUnits1 and 2 3.3.1-11 Amendment 231/212
RTS Instrumentation
3.3.1 SURVEILLANCE
REQUIREMENTS
SURVEILLANCE
SR 3.3.1.16
Neutron detectorsareexcluded
fromresponsetime
testing.FREQUENCY Verify RTS RESPONSE TIMEiswithin limits.18 months on a STAGGERED TEST BASIS North AnnaUnits1 and 2 3.3.1-12 Amendment 231/212
RTS Instrumentation
3.3.1 Table 3.3.1-1 (page1of5)ReactorTrip
System Instrumentation
FUNCTION APPLICABLE
MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE
CONDITIONS
CHANNELS CONDITIONS
REQUIREMENTS
ALLOWABLE VALUE 1.ManualReactorTrip
2.Power RangeNeutronFlux1,23(a),4(a),5(a)
2 2 B C SR 3.3.1.14 SR 3.3.1.14 NA NA a.Hi gh b.Low 3.Power RangeNeutronFluxRate1,2 4 4 D ESR3.3.1.1:::;110%RT P SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 SR 3.3.1.1:::;26%RTP SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16 a.High Positive Rate b.HighNegativeRate
4.Intermediate
RangeNeutronFlux5.Source RangeNeutronFlux1,21,2 4 4 2 2 E EF,GH,I SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16:::;5.5%RTPwithtime constant2sec:::;5.5%RTPwithtime constant2sec:::;40%RTP:::;1.3 E5 cps NA 2 I, J K SR 3.3.1.1:::;1.3 E5 cps SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 SR 3.3.1.1 SR 3.3.1.11 (a)With RodControlSystemcapableofrodwithdrawaloroneor
morerodsnot fully inserted.(b)BelowtheP-I0 (Power RangeNeutronFlux)
interlocks.(c)AbovetheP-6 (Intermediate
RangeNeutronFlux)
interlocks.(d)BelowtheP-6 (Intermediate
RangeNeutronFlux)
interlocks.(e)With the RodControlSystem
incapableofrodwithdrawal.In
this condition,sourcerangeFunctiondoesnotprovide
reactor tripbutdoesprovide
indication.
North AnnaUnits1 and 2 3.3.1-13 Amendment 231/212
RTS Instrumentation
3.3.1 Table 3.3.1-1 (page 2 of 5)Reactor Trip System Instrumentation
APPLICABLE
MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE
FUNCTION CONDITIONS
CHANNELS CONDITIONS
REQUIREMENTS
ALLOWABLE VALUE6.Overtemperature1,23E SR 3.3.1.1Referto SR 3.3.1.3 Note 1 (Page SR 3.3.1.7 3.3.1-16)SR 3.3.1.9 SR 3.3.1.12 SR 3.3.1.16 7.Overpower1,23E SR 3.3.1.1Referto SR 3.3.1.7 Note 2 (Page SR 3.3.1.12 3.3.1-17)8.Pressurizer
Pressure a.Low 1 (f)3 L SR 3.3.1.11860 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 b.Hi gh1,23E SR 3.3.1.12370 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 9.PressurizerWaterLevel-High
1 (f)3L SR 3.3.1.193%SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.1610.ReactorCoolant
Flow-Low 1 (f)3per L SR 3.3.1.189%loop SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 11.ReactorCoolant
Pump (RCP)1 (f)1per M SR 3.3.1.14 NA Breaker Position RCP 12.Undervoltage
RCPs 1 (f)1per L SR 3.3.1.62870 V bus SR 3.3.1.10 SR 3.3.1.1613.Underfrequency
RCPs 1 (f)1per L SR 3.3.1.6(9)56 Hz bus SR 3.3.1.10 SR 3.3.1.16 14.Steam Generator (SG)Water1,23per SG E SR 3.3.1.117%Level-Low Low SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 (f)AbovetheP-7 (Low PowerReactorTripsBlock)
interlock.(g)RequiredtobeperformedforUnit2only.
North AnnaUnits1 and 2 3.3.1-14 Amendment 231/212
RTS Instrumentation
3.3.1 Table 3.3.1-1 (page3of5)Reactor Trip System Instrumentation
FUNCTION 15.SG Water Level-LowCoincidentwithSteam
Flow/Feedwater
Flow Mismatch APPLICABLE
MODES OR OTHER SPECIFIED CONDITIONS1,21,2 REQUIRED CHANNELS2per SG2per SG SURVEILLANCE
CONDITIONS
REQUIREMENTS
E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 ALLOWABLE VALUE24%42.5%fullsteamflowat
RTP16.TurbineTrip
a.Low AutoStopOil Pressureb.TurbineStopValveClosure17.Safety Injection(SI)Input from Engineered
Safety FeatureActuationSystem (ESFAS)lB.ReactorTrip
System Interlocks
a.Intermediate
Range NeutronFlux,P-6 b.Low PowerReactorTripsBlock,P-7 c.Power RangeNeutronFlux, P-B d.Power RangeNeutronFlux, P-10e.TurbineImpulse
Pressure, P-1319.ReactorTrip
Breakers(i)20.ReactorTripBreakerUndervoltageandShuntTrip
Mechanisms21.AutomaticTripLogic1,21,21,2 3 (a), 4 (a), 5 (a)1,21,2 3 (a), 4 (a), 5 (a)3 4 2 trains 21per train 4 4 2 2 trains 2 trains1each per RTB1each per RTB 2 trains 2 trains N N o Q R R Q R P C S C o C SR 3.3.1.10 SR 3.3.1.15 SR 3.3.1.10 SR 3.3.1.15 SR 3.3.1.14 SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.5 SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.10 SR 3.3.1.13 SR 3.3.1.4 SR 3.3.1.4 SR 3.3.1.4 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.540psig0%open NA3E-11 amp NA31%RTP7%RTP11%RTP11%turbine power NA NA NA NA NA NA (a)With RodControlSystemcapableofrodwithdrawaloroneor
morerodsnot fully inserted.(d)BelowtheP-6 (Intermediate
Range Neutron Flux)interlocks.(h)Above the P-B (Power RangeNeutronFlux)
interlock.(i)Includingany
reactor trip bypass breakers thatarerackedinandclosedforbypassingan
RTB.North AnnaUnits1 and 2 3.3.1-15 Amendment 231/212
RTS Instrumentation
3.3.1 Table 3.3.1-1 (page4of5)ReactorTrip
System Instrumentation
Note1:Overtemperature The Overtemperature Function Allowable Value shallnotexceedthe
following nominal trip setpoint by more than 2.0%of span.T:s;T o{K 1-:[T-T']+K 3(P-PI)-f 1}Where: is measured RCS OF. is the indicated at RTP, OF.sistheLaplace
transform operator, sec-I.T is the measured RCS average temperature, OF.T I is the nominal Tavg at RTP,[*]OF.P is the measured pressurizer
pressure, psig pi is the nominal RCS operating pressure,[*]psig K I[*]K 2[*]/oF K 3[*]/psig[*]sec[*]sec f 1=[*]{[*]-(q,-qb)}whenqt-qb<[*]%RTP 0 when[*]%RTPqt-qb[*]%RTP[*]{(qt-qb)-[*]}whenqt-qb>[*]%RTP Where qt and qb are percent RTPintheupper
andlowerhalvesofthe core, respectively, and qt+qb is the total THERMAL POWER in percent RTP.Thevaluesdenotedwith
[*]are specifiedinthe COLR.North AnnaUnits1 and 2 3.3.1-16 Amendment 245/226
RTS Instrumentation
3.3.1 Table 3.3.1-1 (page5of5)ReactorTrip
System Instrumentation
Note 2: Overpower L1T The Overpower L1T Function Allowable Value shallnotexceedthefollowing
nominal trip setpoint by more than 2%of span.Where: is measured RCS OF. is the indicated L1T at RTP, OF.s istheLaplace
transform operator, sec-I.T is the measured RCS average temperature, OF.T I is the nominal Tavg at RTP,[*]OF.K 4[*]K 5[*]jOF for increasing
Tavg[*]jOF for decreasing
Tavg K 6[*]jOF when T>T I[*]jOF when TT I Thevaluesdenotedwith[*]are
specifiedinthe COLR.North AnnaUnits1 and 2 3.3.1-17 Amendment 231/212
Spent Fuel Pool Storage 3.7.18 45000.....---.....--........----.,---.......--.......---.------.--
......4.6 4.2 3.8 Unacceptable
3.4 3 2.6 2.2 Acceptable
1.8
......--_+_--_+_--_+--__t
1.4 15000+-----+------+----#-----1---+----1---+-----+----+-----1
10000-I-----t-----#----+------I-'l---+-----+-----+-----+------I
30000+----t-------+------I---+------#------+-----+--.'---I
35000
5000
40000+----t-------+------I---+-----+------+-----+-#------II
5':E C 3:25000+----t-------+------I----#-----+------+-----#---+------II
Q,:::s e:::s co:c E 20000+----t-------+------I-#---+-----+---#-----+-----+------II
Q)tn tn<<-;:::s u, Initial U-235 Enrichment (nominal w/o)Acceptable:
Acceptable
for storage in non-matrix
locationorlow reactivity
locationinmatrix configuration.Mayalsobe placedinhigh reactivity
locations in matrix configuration.
Conditionally
Acceptable:
Acceptableforstoragein
non-matrixlocation,butmustbeplacedinhigh reactivity
location if storedinmatrix configuration.
Unacceptable:
Must be storedinhigh reactivity
location in matrix configuration.Surryspentfuelmustbe
storedinhigh reactivitylocationsina
matrix.Figure 3.7.18-1(page1of1)
Burnup Credit Requirements
North AnnaUnits1 and 2 3.7.18-3 Amendments
231/212
Inverters-Operating
3.8.7 3.8 ELECTRICAL
POWER SYSTEMS 3.8.7 Inverters-Operating
LCO 3.8.7 TheTrainH and Train J inverters shall be OPERABLE.------------
NOTE-----------
One inverter maybedisconnected
from its associated
DC bus for24hourstoperforman
equalizing
charge on its associated
battery, provided: a.The associated
AC vital bus is energized from its constant voltage source transformer;
andb.All other AC vitalbusesare energized from their associated
OPERABLE inverters.
APPLICABILITY:
MODES1,2,3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION
TIME A.One inverter A.1---------NOTE--------
Enter applicable
Conditions
and RequiredActionsof LCO 3.8.9, IIDistribution
Systems-Operati
nq" with any vital bus de-energized.
Restore inverterto7 days OPERABLE status.B.Required Action and B.1 Be in MODE 3.6hours associated
Completion
Timenotmet.AND-B.2 Be in MODE 5.36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> North AnnaUnits1 and 2 3.8.7-1 Amendments
235/217
SURVEILLANCE
REQUIREMENTS
SURVEILLANCE
Inverters-Operating
3.8.7 FREQUENCY SR 3.8.7.1 Verify correct inverter voltage andalignmentto
required AC vital buses.7 days North AnnaUnits1 and 2 3.8.7-2 Amendments
231/212
Distribution
Systems-Operating
3.8.9 3.8 ELECTRICAL
POWER SYSTEMS 3.8.9 Distribution
Systems-Operating
LCO 3.8.9 The following distribution
subsystems
shall be OPERABLE: a.TheTrainH and Train J AC, DC, and AC vital buses;and b.One AC and DC bus on the other unit for each required shared component.
APPLICABILITY:
MODES1,2,3, and 4.ACTIONS CONDITION A.One or more LCO 3.8.9.a AC electrical
power distribution
subsystem(s)
North AnnaUnits1 and 2 A.l REQUIRED ACTION
Enter applicable
Conditions
and RequiredActionsof LCO 3.8.4, IIDC Sources-Operating, II for DC train(s)made inoperable
by inoperable
distribution
subsystem(s).
Restore AC electrical
power distributionsubsystem(s)to
OPERABLE status.3.8.9-1 COMPLETION
TIME8hours AND 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> fromdiscoveryof
failure to meet LCO Amendments
231/212
ACTIONS Distribution
Systems-Operating
3.8.9 CONDITION REQUIRED ACTION COMPLETION
TIME B.One or more B.1 Restore AC vital bus2hours LCO 3.8.9.a AC vital subsystem(s)
to bus(es)inoperable.
OPERABLE status.AND-16 hours from discovery of failure to meet LCO C.One or more C.1 Restore DC electrical2hours LCO 3.8.9.a DC power distribution
electrical
power subsystem(s)
to AND distribution
OPERABLE status.-subsystem(s)
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from inoperable.
discovery of failure to meet LCO D.--------NOTE----------
D.1 Declare associated
Immediately
Separate Condition shared component(s)
entry is allowed'for inoperable.
each AC subsystem.
One or more required LCO 3.8.9.b AC electrical
power distribution
subsystem(s)
E.--------NOTE----------E.1Declare
associated
Immediately
Separate Condition shared component(s)
entry is allowed for inoperable.
each DC subsystem.
One or more required LCO 3.8.9.b DC electrical
power distribution
subsystem(s)
North AnnaUnits1 and 2 3.8.9-2 Amendments
231/212
Distribution
Systems-Operating
3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION
TIME F.Required Action and F.1 Be in MODE 3.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated
Completion
Time for Condition A, AND B,orCnotmet.
-F.2 Be in MODE 5.36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> G.Two or more G.1 Enter LCO 3.0.3.Immediately
LCO 3.8.9.a electrical
power distribution
subsystems
that resultina loss of safety function.SURVEILLANCE
REQUIREMENTS
SR 3.8.9.1 SURVEILLANCE
Verify correctbreakeralignments
and voltage to required AC, DC, and AC vital bus electrical
power distribution
subsystems.
FREQUENCY 7 days North AnnaUnits1 and 2 3.8.9-3 Amendments
231/212
GENERIC FUNDAMENTALS
EXAMINATION
EQUATIONS AND CONVERSIONS
HANDOUT SHEET EQUATIONS Q=milh Q=UAilT*.3 Q oc mNat Cire il T ec
Cirep=(K e ff-1)/K e ff SUR=26.06/-17 13eff-p't=Aeff p Q*13eff p=-+---r 1+Aeff r Q*=1x10-4 sec A e ff=0.1 sec"(forsmallpositivep)22 DRW oc<Ptip/<Pavg P=P10SUR(t)o P=P e(th)o A=A e-At o F=PA ill=pAy W-milPuPump-E=IRThermalEfficiency
=NetWorkOut/EnergyIn
g(Z2-ZI)+(V 2 2-"1 2)+u(P 2-PI)+(u 2-u.)+(q-w)=0gc2g c gc=32.2 lbm-ft/lbf-sec'
CONVERSIONS1Mw=3.41 X 10 6 Btu/hr1Curie=3.7x1010 dps1hp=2.54x10 3 Btu/hr1kg=2.21Ibm1Btu=778 ft-lbf 1 galwater=8.35Ibm°C=(5/9)(OF-32)1 W water=7.48gal OF=(9/5)(OC)+32-3-