ML20260H166
| ML20260H166 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/30/2020 |
| From: | Todd Fish, Velma King Operations Branch I |
| To: | Exelon Generation Co |
| Fish T | |
| Shared Package | |
| ML19105A151 | List: |
| References | |
| CAC: 000500 | |
| Download: ML20260H166 (304) | |
Text
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xe 2020NRCROExamrevo Test ID: 330066 f/35///N/JffiffffffffN////fNMJAir7/2t2%ff/Jff///fff/////ffaif851 Unit3isat100% power e TheUnit 3 HPCITurbine isolated from a false steam supply lowpressure signal.
a I&CTechnicians corrected the problem,the isolation signalisclear.
e Nooperator actions have been performed inthe Main Control Room.
a RPVpressure is1034 psig.
Subsequently atransient causes RPV level tolower to-55inches.
Which ofthefollowing automatic and/ormanual actions willresult inHPCIsystem start?
A. TheHPCIisolation resets automatically, the steam supply valves(MO-15 andMO-16) mustbemanually re-opened.
B. TheHPCIisolation resets automatically, the steamsupply valves(MO-15 andMO-16) willautomatically open.
C. Pushbuttons 23A-S20 (AUTO/MANUAL RESET) and 23A-S26 (AUTO RESET) must be depressed ONLY.
D. Pushbutton 23A-S20 (AUTO/MANUAL RESET) and23A-S26 (AUTO RESET) must be depressed ANDtheSteam Line IsolationValves (MO-15 and MO-16) mustbemanually re-opened.
Answer: B Answer ExplanationE .
Justification: Choice Basis orJustification Correct: B TheHPCIlowsteam supply pressure signal isolation will auto reset above 100psig reactor pressure. Thesteam supplyvalves will open automatically on-48inches RPVlevel initiation signalonceisolation auto resets.
Distractors: A Thesteam supply valves will openautomatically on-48inches RPV level initiation signal. Plausible aseven though theisolation signal is clear, thesystem wasstill isolated andthe candidatemay misinterpret that theall valves will notrealignforinjections C Noisolation reset pushbuttons needtobedepressed. TheHPCIlow steam supply pressure isolation signalwill autoresetabove 100psig reactor pressure. Plausible ifthe candidate the misinterprets isolation signal asonethat doesnotauto reset.
D Noisolation reset pushbuttons need tobedepressed. TheHPCIlow steam supply pressure isolation signalwill autoresetabove 100psig reactor pressure. Plausible ifthe candidate the misinterprets isolation signal asonethat does not auto reset.Plausibleaseven after the isolation signal isclear, the system wasstillisolated andthe candidate maymisinterpret that theallvalves willnotrealign for in~ection.
Page:1of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Questioniinfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 3 Difficult: 3.50 S stemID: 994374 User-Defined ID: ILT-5023-4G-003 Cross Reference Number: 206000 K1.02 Topic:
. ILT-5023-4G-003 TheUnit 3HPCITurbine isolated from a faultlow steam su I ressure sinal.
NumField 1: 0.00 NumField 2: 0.00 Text Field:
Comments:
Ps chometrics Level of Diffic Time RO Knowledge ultyAllowance minutes HIGH 10CFR55.41(b)(7)
Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other Exam Bank X ILTExamBank Reference s : SO23.7.C-3 Learning PLOT 5023 -
Ob^ective:
K/ASystem: 206000HPCI -
Importance:
RO/SRO 4.0/ 4.1 K/AStatement: K1.02Knowledge ofthephysical connections and/or cause-effect relationships between HIGHPRESSURE COOLANT INJECTION SYSTEM andthe followin :Reactor water level REQUIRED NONE MATERIALS:
Notes and Comments:
Page:2 of214 16March2020
=. .
2020NRCROExamrev0 TestID:
330066
$MWAWANAMAGY[AlflffkfMffhblfffdflfdk[ffff2$hDA Whichofthefollowing canbeused for depressurization alternate totheMain Condenser using T-252-2 "RPVAlternate Depressurization /RPVVenting"?
- 1. HPCIsteam line drain
- 2. RCICsteam linedrain
- 3. BPVs
- 4. RWCU A. 1,2,and3 B. 1,2,and4 C. 1,3,and4 D. 2,3,and4 Answer: A Answer Explanation Justification: Choice Basis orJustification Correct: A Thesystems used foralternate depressurization that canbeused out ofT-252-2areHPCI, RCIC, BPV's, Main Steam line drains,Reactor Feedpumps,andSteam Air Jet Ejectors/Offgas System.
Distractors: B PlausibleasBothHPCI andRCIC canbeused in T-252-2. RWCU canbeused depressurization asanalternate path, however that is controlled underT-227 bypassing if interlocks isnecessary.
C PlausibleasBothHPCI andBPV's canbeused inT-252-2. RWCU canbeused asanalternate depressurization path, however that is controlled underT-227 bypassing if interlocks isnecessary.
D PlausibleasBothRCICandBPV's canbeusedinT-252-2. RWCU canbeused asanalternate depressurization path, however that is controlled underT-227 if bypassing interlocks isnecessary.
Page:3of214 16March2020
2020NRCROExamrev0 Test ID:330066 Question2 info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: O Difficul : 2.00 S stem ID: 2132439 User-Defined ID:
Cross Reference Number: 217000 K1.04 To ic: PLOT-5013-5d-002 RCICT-252 NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Diffic Time RO KnowledgeultyAllowance minutes Memory 10CFR55.41(b)(10)
Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other Exam Bank ILTExamBank Reference s : T-252-2, T-112 Learning PLOT -
5013-5d Ob'ective:
K/ASystem: 217000RCIC -
Importance:
RO/SRO 2.6/ 2.6 K/AStatement: K1.04Knowledge ofthephysical connections and/or cause-effect relationshipsbetween Reactor Core IsolationCooling System (RCIC) andthe followin :Main Condenser REQUIRED NONE MATERIALS:
Notes and Comments:
Page:4 of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 AFAsT$illi#edh WM%D)ffff/NMM$WWAAYAKW#25tWFTWEFAkiiinarate 2 is Unit operating at 80% power whena loss ofthe 2ARPSMGSet occurs.
Whichoneofthe following identifies the expected Power Range Neutron Monitor/plant response assumingnooperator action?
A. APRMChannels "1"and"3" lose power.
B. APRMChannels "2" and "4" lose power.
C. TwoQuadLowVoltagePower Supplies loseall input power.
D. AII QuadLowVoltage PowerSupplies lose oneofthe input power supplies.
Answer: D Answer Explanation : . . . . . . . . .
Justification: Choice Basisor Justification Correct: D TheAPRM's arepowered bythe Quad Low VoltagePower Supplies that have a supply fromboththe "A"RPS and the "B"RPS.When either RPSbusloses power theother will supply power tothe APRM's without interruption.
Distractors: A Plausible if thecandidate misinterprets the power supplies of the APRM's being the QuadLowVoltage Supplies and the 2/4 logic voters that get their power directly from RPSbus.If the "A"RPSbus loses power, voters 1and3which arerelated toAPRM's "1"and"3" would lose power. Each APRMchassis hasanalternate power Supply B Plausible if the candidate confuses the power supplies oftheAPRM's being the QuadLowVoltage Supplies andthe 2/4logic votersthat get their power directlyfrom RPSbus. The"B"RPSbuswould be related tovoters 2 and4 whicharerelated tothe"2" and"4" APRM's.
Each APRMchassis hasan alternate power supply. .
C Plausible if candidate misinterprets the electrical supplies tothe Quadlow Voltage Power Supplies. EachQuadLowVoltage Power Supply hastworedundant powersupplies (RPS 'B').
'A'and Page:5 of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Question 3Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 2 Difficult: 3.00 S stemID: 994278 User-Defined ID: A-lLT-5060-6A-002 Cross Reference Number: 215005K2.02 Topic: A-ILT-5060-6A-002 Unit2 isoperating at80%power whena lossof the 2ARPSMGSet occurs. Which NumField 1: 0.00 NumField 2: 0.00 Text Field:
Comments:
Ps chometrics Level of Diffic Time RO Knowledgeulty Allowance minutes Memory 10CFR55.41(b)(7)
Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other Exam Bank X ILTExamBank Reference s: PLOT5060;M-1-S-34 shts36 & 37 Learning PLOT 5060 Ob'ective:
K/ASystem: 215005APRM/LPRM Importance:
RO/SRO 2.6/ 2.8 K/AStatement: K2.02Knowledge ofelectricalpower su lies tothe followin :APRMChannels REQUIRED NONE MATERIALS:
Notes and Comments:
Page:6of214 16March 2020
2020NRCROExamrev0 Test ID:330066 AGE4%$$$jffffffffAff$$$fffff$f$5$WA$$)$$J$RfMTWAjV/ffffffffff@/$FME Which ofthe following describes the power supply tothe Unit 2'A' RBCCW pump?
A. 480VAC DIVIE-Bus B. 480VACDIV II E-Bus C. 480VACDIVINon-Emergency Bus D. 480VACDIVII Non-Emergency Bus Answer: A Answe;r Explanationnn .'
. . cA .. . .. LL. ... . . . ..... .. .
Justification: Choice Basis or Justification Correct: A The2ARBCCW pumpis powered byE-324-R-D, which isa Division I,safetyrelated E-Bus.
Distractors: B Plausible asthe 2BRBCCW pump ispowered bya Division II,safety relatedE-Bus andthe candidate may confuse the two.
C Plausible asthe 2ATBCCWpumpispowered bya DivisionI, non-safety related Busandthecandidate may confuse the two.
--Plausible D asthe 2BTBCCW pumpispowered bya Division II, non-safety related Busandthe candidate mayconfuse the two.
Page:7 of214 16March 2020
2020 NRCROExamrev0 Test ID:330066 Question4ilnfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 1 Difficult: 2.00 S stemID: 993347 User-Defined ID: ILT5035-PWRTO2APMP Cross Reference Number: 400000 K2.01 ,
To ic: ILT-5035-001 Power Su I to2ARBCCW Pum NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Diffic Time RO Knowledgeulty Allowance minutes Memory 10CFR55.41(b)(7)
Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other ExamBank X ILT ExamBank Reference(s): PLOT5035, E-1617 Learning PLOT 5035 Ob'ective:
K/ASystem: 400000- Component Importance:
Cooling Water System RO/SRO CCWS 2.9/ 3.0 K/AStatement: K2.02Knowledge ofelectricalpower su lies tothe followin :CCW um s REQUIRED NONE MATERIALS:
Notes and Comments:
Page:8 of214 16March 2020
ix x 2020NRCROExamrev0 Test ID:330066 WWidBW/kWhirfWW/fA$AMWWfffMYAfkkkW4[hkl$$VAD Unit 3isat100% power with the following condition e -QaeRPSChannel A GroupWhiteLight onPanel 30C015 isNOTlit duetoa blown fuse.
During trouble shooting the 3B RPS MGset output breaker spuriously trips.
ofthe Which followingdescribes the effect onthe Control Rods?
A. ONLY1/4 ofthecontrol rods willinsert B. ONLY 1/2ofthe control rods will insert C. Allofthe control rods will insert D. None ofthecontrol rods will insert Answer: A Answer ExplanationL ...... . ....... . . . .. ... ...... . .. . .. . ..... . . .
Justification:
Choice Basis orJustification Correct: A With oneGroup white lightout onRPSchannel A,1/4 ofthe control rods have onescram solenoid without power on the 'A' channel.
Whenthe3BRPSMGset output breaker spuriously trips, removes it power from the 'B'channel scram solenoid for all control rods.
Therefore 1/4 ofthecontrol rods donothave power to either solenoid valve andwill insertinto thecore.
Distractors: B Plausible because allcontrol rods have 1/2 ofthe scram solenoids without power duetothe loss oftheB MGset. This however will not cause anyofthe control rods toscram.
C Plausible if the candidate misinterprets thesignificance ofthe white lights onPanel 30C015 andconsiders theblown fuse asequal toan entire loss ofChannel A RPS.
D Plausible if thecandidate misinterprets thesignificance ofthe white lights onPanel 30C015 andconsiders theloss ofthe white light just a loss ofindication andnota loss ofpower toscram solenoid valves, which would betrue if onlthe lihtbulb wasblown andnotthefuse.
Page:9 of214 16March 2020
i 2020NRCROExamrev0 Test ID:330066 Question; 5info.. ... . . . . . . .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 3 Difficul : 2.00 S stem ID: 994488 User-Defined ID: ILT-5060F-3A-006 Cross Reference Number: 212000 K3.07 To ic: ILT-5060F-3E-006 Loss ofonewhite liht NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Diffic Time RO Knowledgeulty Allowance minutes High 10CFR55.41(b)(6)
Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other ExamBank X ILT ExamBank Reference(s): M-1-S-54 Learning PLOT 5060F -
Ob^ective:
K/ASystem: 212000Reactor -
Importance:
Protection System RO/SRO 3.8/ 3.9 K/AStatement: K3.07Knowledge ofthe effect thata loss ormalfunction oftheReactor Protection System will haveonthe following: Reactor Powerthermal heat flux REQUIRED NONE MATERIALS:
Notes and Comments:
Page: 10of214 16March 2020
i; 2020NRCROExamrev0 Test 330066 ID:
A332% f/////f////ffff////fAfd hWM/Af?ff//ff#///////////fM Unit 3isinMODE 4, twenty-four hours after shutdown,followingextended power full with operationthe following conditions:
= "B" Reactor Recirculation pump is inservice
= MSlVs All areclosed a 3CResidual Heat Removal (RHR) pump isoperatingintheShutdown Cooling Mode
= ReactorCoolant Temperature is 135 0Fona very slow downward trend
- Reactorwater level isbeing maintained at+30inches A spurious
+1inch lowreactor water level signal isreceived Whichofthe following describes theplant response:
The3CRHRpumpwill --(1)-
AND The3BRecirculation loop temperatures will(21 A. (1) Trip (2) Stay consistent with RPVTemperature B. (1) Trip (2) Begin todiverge from RPVTemperature C. (1) Continue torun (2) Stay consistent with RPVTemperature D. (1) Continue torun (2) Begin todiverge from RPVTemperature Answer: A Page:11of214 16March 2020
=
2020NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: A Thelowreactor water level willcause SDCvalves MO-17andMO-18 valves toclose. This willcause a loss ofSDCandthe 3CRHRpump totrip. The3Brecirculation pumpwill continue torun andmaintain temperatures consistent with coolant intheReactor.
Distractors: B The first part istrue andthe 3CRHRpumpwill Thesecond trip. part is plausible because ifthe spurious signal were a2 psiginthe Drywell signal, SDCwould belost andthe discharge MO-53of valves both recirc pumps would close. TheMO-53 closurecomesfroma combination ofa LPCI injection 450psigRPV pressure) AND< 211psig signal (> 2 psig inthe RPVpressure.
Drywell and<
Thestem states however that itisa spurious lowlevel inthereactor.
C First part isplausible if candidate misinterprets thesignals that would give a loss ofshutdown cooling. Second part istrue.
D First part isplausible if candidate misinterprets thesignals that would give a loss ofshutdown cooling. Thesecond partisplausible because ifthe spurious signal were a 2 psig intheDrywellsignal, SDCwould belost andthe discharge valves MO-53 ofbothrecirc pumps would close. TheMO-53 closure comes from acombination ofa LPCI pressure) injection AND 211psig signal (> 2 psig inthe Drywell and< 450psig RPVpressure. The stemstates RPV however that itisa s urious lowlevel inthe reactor.
Page: 12of214 16March 2020
2020NRCROExamrevo Test ID: 330066 Questioni6!kifo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 2 Difficul : 3.00 S stem ID: 2123351 User-Defined ID: ILT-5010-6G-001 Cross Reference Number: 205000 K3.04 To ic: ILT-5010-6 -001Loss ofSDCwith Recirc inservice NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Diffic Time RO Knowledgeulty Allowance minutes High 10CFR55.41(b)(7)
Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other ExamBank ILTExamBank Reference(s): PLOT5010, 5002 TS3.3.5.1 Learning PLOT 5010 -
Ob'ective:
K/ASystem: 205000Shutdown Importance:
Cooling System (RHR RO/SRO Shutdown Cooling 3.7/ 3.7 Mode K/AStatement: K 3.04Knowledge ofthe effect a that ormalfunction loss oftheShutdown Cooling System (RHR Shutdown Cooling Mode) will have onthefollowing:
Recirculation Loo Tem eratures REQUIRED NONE MATERIALS:
Notes and Comments:
Page: 13of214 16March 2020
i 2020NRCROExamrevo TestID: 330066 ggy tygvjgiyfrjjfjjjgyjjQeffj)ffjffff j;)fgQQlQyMfjfigggfjfgfffgg$gdigpjgM Unit 2isinMode 5 with refueling activitiesinprogress
= Anirradiated fuelbundle is dropped a Reactor Building andRefuel Floor Exhaust Radmonitors indicate asfollows:
ReactorB.ldgExha.ust h Ch. A 9mR/hr Ch. A 8mR/hr Ch.B 8mR/hr Ch.B 8 mR/hr Ch. C 18mR/hr Ch.C 9mR/hr Ch.D 22mR/hr Ch.D 32mR/hr onthe Based above indications, howwill ReactorBuilding Ventilation andSBGT without respond operator action?
A. Reactor Building ANDRefuel Floor Ventilation continue tooperate.
SBGTdoes NQIinitiate.
B. Reactor Building Ventilationisolates.
SBGTinitiates andaligns totheReactor Building ONLY.
C. Refuel Floor Ventilation isolates.
SBGTinitiates andaligns totheRefuel Floor ONLY.
D. Reactor Building ANDRefuel Floor Ventilation isolate.
SBGTinitiates andaligns totheReactor Building ANDRefuel Floor.
Answer: D Page: 14of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Choice Basis orJustification Correct: D GRIll isolation hasoccurred. PCIS logic isA orCANDB orD; setpoint is16mR/hr (10 mR/hr per ARC). EitherRBorRFlogic channels will isolate RBANDRFventilation. Inthegiven conditions, afull-isolation ispresent onReactor BIdg Exhaust Rad Monitors. SBGT will initiate ifRPVlevel is1inorDWpressure is2 psig orthe correct combination ofRBand/or Refuel ventilation floor radiation levels above 16mr/hr.
Dwhich isthelogic for Control RoomEmergency Ventilation B Plausible if the candidate misinterprets the logicoftheGRIll isolation and that the ventilation system theinitiation with will signal bethe only one SBGT will aligns to.
C Plausible the if candidate misinterprets the logicoftheGRIII isolation andthat the SBGT system will align totheventilation system with the highest rad reading.
Page: 15of214 16March 2020
C n::::.
s:::A: = = ::: n : :=
liii A
2020NRCROExamrevo Test ID:330086 Question;1info Question T e: Multi leChoice Status: Active Alwa sselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 3 Difficult :
2.00 S stemID: 2123353 User-Defined ID:
Cross Reference Number: 261000 K4.01 To ic: ILT-5009A-3B SBGTinitiation NumField 1:
NumField 2:
Text Field:
Comments: Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes HIGH 10CRF55.41(b)(
13 Source Documentation Source: NewExamitem Previous NRC Exam X Modified Bank Other ExamBank (2114315)
ILT ExamBank Reference s: GP-8.B; GP-8.B COL Learning PLOT-1550 27b Ob'ective:
K/ASystem:261000Standby -
Gas Importance:
Treatment System RO/SRO 3.3/3.5 K/A K4.01Knowledge ofStandby Gas Statement:Treatment System design feature(s) and/or interlocks which provide for the following:
Automatic s steminitiation REQUIRED None MATERIALS:
Notes and None Comments:
Page: 16of214 16March 2020
2020 NRCROExamrev0 Test ID:330066
$DN%W@#2$W7/fAV1744tW&%WMAW5W$5%i9t##WiWf7&@*?WiiPAT4KAfA&
Unit2 is at100% power with the following conditions:
= SO57B.7-2 "U2Alternate 125VDCStation Battery Charger Operations" 20D390 isperformed to the place alternate battery charger in service tothe 2AD001 batteries.
station Which oneofthe following describes the plant impact?
While to2AD001 aligned battery the U2 Alternate 125VDCStation Battery --(1)--
Charger power supply toanother battery.
station AND lfa loss ofoffsite power occurs the 2AD001 battery loads byA besupplied will A. (1) can (2) 2AD001 Battery ONLY B. (1) cannot (2) 2AD001 Battery ONLY C. (1) can (2) U2Alternate 125VDCStation BatteryCharger D. (1) cannot (2) U2Alternate 125VDCStation BatteryCharger Answer: B Page: 17of214 16March 2020
s p=a:e 77 n wn = n m 4emfn 2020NRCROExamrevo Test ID:330066 Choice Basis orJustification Correct: B Inaccordance with SO57B.7-2, the alternate battery chargercan only supply oneUnit 2station battery ata time. TheAlternate 125 VDCbattery charger isnot supplied byanE-Bus andif a Lossof Offsite power were tooccur, the charger would lose power andnot supply theloadsAthe battery would besupplyingtheIoads.
Distractors: A Plausible ascandidate maymisinterpret that because theAlternate 125VDC Station battery charger canbeusedtomaintain battery voltages onanyofthefour Unit 2 station batteries, thatit candoit simultaneously. However, only onestation battery canbesupplied ata time.
Thesecond part iscorrect C Plausible as candidate maymisinterpret that because theAlternate 125VDC Station battery charger canbeused tomaintain battery voltages onany ofthe four Unit 2 station batteries, thatit candoit simultaneously. However, only onestation battery canbesupplied atatime.
Plausible ifthe candidate misinterprets the electrical lineupand supplies oftheAlternate battery chargerandthat it lose will power dunng a LOOP.
D First part iscorrect.
Second part isplausible the if candidate misinterprets theelectrical lineup andsupplies ofthe Alternate battery chargerandthat it will loseower durin a LOOP.
Page: 18of214 16March 2020
f j:
2020NRCROExamrev0 Test ID:
330066 Question:8info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 2 Difficul : 2.00 . .
S stemID: 2123439 User-Defined ID: PLOT-5057-3B-001 Cross Reference Number: 263000 K4.02 Topic: PLOT-5057-3b-001 U2Alternate 125VDC Station Battery Charer NumField 1:
NumField 2:
Text Field:
Comments: Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes Memory 10CRF55.41(b)(
10 Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other Exam Bank ILTExamBank Reference s : SO57B.7-2 Learning PLOT-5057-3b Ob'ective:
K/ASystem:263000- DCElectrical Importance:
Distribution RO/SRO 3.1/ 3.5 K/A K4.02Knowledge ofD.C. Electrical Statement: Distribution design feature(s) and/or interlocks which provide for thefollowing:
Breaker interlocks, permissives, bypasses andcross ties REQUIRED None MATERIALS:
Notes and None Comments:
Page: 19of214 16March2020
g e
2020NRCROExamrev0 Test ID: 330066 Ad@$%MAf53%Nd$7f3N/AbdMWf)$AkhMiWfAki&$WWIWAA Giventhefollowing:
Attime= 0 a Reactor pressure is 550 psig Whichoneofthe following list of plant conditions willdirectly result inthe automatic opening ofthe ADS?
A. 2.5psig Drywell pressure concurrent with
-165inches Reactor water level for1minute, allRHRPumps running B. 1.5psig Drywell pressure concurrent with
-165inches Reactor water level for5 minutes, withONLYthe "D"RHRPumprunning C. 2.5psigDrywell pressure concurrentwith -165 inches Reactor water level for5 minutes, withthe
'A' and'C' Core Spray Pumpsrunning D. 1.5psigDrywell pressure concurrent with
-165 inches Reactor water level for12 with minutes, the 'A' and'B' Core Spray Pumps running Answer: C Answer Explhitatione Choice Basis orJustification Correct: C Thelevel i's'<'-160inches inthe RPV,there is > 2 psig in the drywell, greater than115seconds haspassed,and there isthe correct combination ofpumps running, therefore ADS will initiate.
A-"' Filausible Distractors: ifcandidate misinterprets initiation signals asthere is an additional 115second timer thatinitiates after< -160 inches reactor leveland> 2 psig inthedrywell. Inthis setup only 60seconds has passed.
B Plausible ifcandidate misinterprets theinitiation signals asthereis a 9.5minute timer thatstartswhenlevel is<-160 inches. This timer will bypass the> 2 psig inthedrywell logic, however not enough time haspassed tobypass the> 2 psig inthedrywell logic.
Thecandidate mayconfuse this timerwiththe 115second timer.
D Plausible ifthecandidate misinterprets thecombination ofLow Pressure ECCSpumps inservice. Toinitiate ADS1RHRpump needs tobeinservice, orthecorrect combination ofCore Spray pumps. Those combinations being "A" or"B"pumpand"C" or"D" um Other combinations willnotinitiate ADS.
Page: 20of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Questiong9 Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoCom lete: 3 Difficul : 2.00 S stemID: 993544 User-Defined ID: ILT-5001G-5-002 Cross Reference Number: 218000K501 ,
To ic: ILT-5001G-002 Select the conditions that cause ADStoactuate NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes Memory 10CRF55.41(b)(
7 Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other ExamBank X ILTExamBank Reference s : M-1-S-52 sheets 2and3 Learning PLOT-5001G-5 Ob'ective:
K/ASystem: 218000Automatic importance:
Depressurization SystemRO/SRO 3.8/
3.8 K/A K5.01Knowledge oftheoperational Statement:implications ofthe following as concepts they apply toAutomatic Depressurization S stem: ADSloic o eration REQUIRED None MATERIALS:
Notes and None Comments:
Page: 21of214 2020 16March
2020NRCROExamrevo Test ID: 330066 j$MgigjgAAAyldkmgyjfffjf/fffffM(($i(t%f11Q$AW figltfffffffgf@iQ$iji&#pfJjgjiejgioo Unit 2isinanATWS
= T-211-2 "CRDSystem Non-Enriched Boric Acid andBorax Injection" inprogress iscurrently Which oneofthe followingcomplete the statements:
Cold Shutdown Boron Weight has been achieved when--(1) . ofeachchemical hasbeen injected AND Cold Shutdown Boron Weight will maintainthe reactor shutdownunder -(2)-.
A. 1)1550Ibs(Approximately 1/2of the barrels)
- 2) allconditions B. 1) 3850lbs (Allofthebarrels) 2)all conditions C. 1) 1550 Ibs (Approximately 1/2 ofthebarrels) 2)rated pressure conditions ONLY D. 1) 3850lbs (Allofthebarrels) 2)rated pressure conditions ONLY Answer: B Answer ExplanadoN A ... . . . P Choice Basis orJustification Correct: B Inaccordance with T-211 whenthe3850lbsofeachchemical are injected Cold Shutdown Boron Weighthasbeenachieved. In accordance with T-BAS Cold Shutdown Weight Boron willmaintain the reactor shutdown under conditions all Distractors: A Plausible as1550lbs islisted inT-211,however thisistheweight associated with HotShutdown BoronWeight.
Second part iscorrect C Plausible as1550 lbsislisted inT-211,however thisisthe weight associated with HotShutdown BoronWeight.
Plausible asthis iswhatHotShutdown Weight Boron could achieve andthe candidate maymisinterpret the twowith regards of what they allow.
D First part iscorrect Plausible asthis iswhatHotShutdown Boron Weightcould achieve andthe candidate maymisinterpret the twowith regards of what theallow.
Page: 22of214 16March 2020
s . s -
m ... .. . n x .
2020 NRCROExamrevo Test ID: 330066 QuestionLtotl:nfo . . x . .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 3 Difficult: 2.00 S stemID: 2130724 User-Defined ID: ILT-5011-4B-003 Cross Reference Number: 211000 K5.03 To ic: ILT-5011-4b-003 SBLCshutdown Marin NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes Memory 10CRF55.41(b)(
5 Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other Exam Bank ILTExamBank Reference s : T-211, T-BASTRIP Learning PLOT-5011-4B Ob'ective:
K/ASystem: 211000Standby -
LiquidImportance:
Control System RO/SRO 3.2/
3.5 K/A K5.03Knowledge ofthe operational Statement: implications ofthefollowing as concepts they apply toStandby Liquid Control S stem: Shutdown marin REQUIRED None MATERIALS:
Notes and None Comments:
Page: 23of214 16March 2020
- 7 , ,
2020NRCROExamrev0 Test ID:330066
';gjP%&j,f(fgjQ(ffjfgfgj$fffgifffffj jQ1fMfffgggfgfQffffjgfffgjQ@(gjffgyggj Which oneofthefollowing would becorrect concerning the'D' SRVtailpipe vacuum breaker failingto open asdesigned?
A. Direct pressurization ofPrimary containment during the fitst'D'SRVactuation B. Damage tothe T-quencher during fitst'D'SRVactuation C. Direct pressurization of Primary containment during the secoBd 'D'SRVactuation D. Damage tothe T-quencher during secoad'D' SRVactuation Answer: D Answer Explanation Choice Basis orJustification Correct: D Ifthe vacuum breakerfailed toopen avacuum would form inthe SRVanddraw water from the Torus back intothe tailpipeduring the SRVactuation.
first Under these circumstances a second opening ofthe SRVwould cause water hammer in the tailpipe which inturn could cause damage to the T-quencher andits supports.
Distractors: A Plausible asthis would occur if theSRV vacuum breakerfailed in the open direction before SRVactuationand the candidate may misinterpret the functional failures andconsequences ofanSRV vacuum breaker failure. Onthefirst actuationof the SRV, the steam would take the path ofleast resistance and exit outthe vacuum breaker bypassing torus suppression anddirectly pressurize theDrywell.
B Plausible asdamage tothe T-quencher isthe concern, however this willonly occur aftertheSRVhasbeenactuated once and the condensing steam hasvacuumed upwater into the SRVtailpipe.
Atthis time asecond actuation would cause waterhammer damage tothe T-quencher.
C Plausible asthesecond actljation oftheSRViswhat would cause damage during a failureofanSRVvacuum breaker toopen, however direct pressurization isafailure ofthe SRVvacuum breaker toreclose aftero eninasdesi ned.
Page: 24of214 16March 2020
7 7 n
2020NRCROExamrev0 Test ID:330066 Question111nfo Question T e: Multi leChoice Status: Active Alwa sselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 2 Difficult: 2.00 S stemID: 993208 User-Defined ID: ILT-5001A-3M-001 Cross Reference Number: ,
239002 K6.05 To ic: ILT-5001A-3m-001 SRVTail ievacuum breaker stuck shut NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes Memory 10CRF55.41(b)(
7 Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other Exam Bank X ILT ExamBank Reference s : PLOT-5001A, T-102 bases, M-351 Learning PLOT-5001A-3m Ob'ective:
K/ASystem: 239002Relief/Safety Importance:
Valves RO/SRO 3.0/ 3.2 K/A K6.05Knowledge ofthe effect that a loss Statement: ormalfunction ofthefollowing willhave on theRelief/Safety Valves; Discharge line vacuum breaker REQUIRED None MATERIALS:
Notes and None Comments:
Page: 25of214 16March 2020
2020NRCROExamrev0 Test ID: 330066
- A$$#*& YiVARMf?fffdfiff$#fffjAAM2iffj$jRffifyWAQ$kgN$2Ag$$$RiiffiliM$5M Unit 2isoperating at 100% power e Anelectricaltransient results inGroup IAI NDGroup IIIINB-QARD isolations.
oneofthefollowing Which is correct regarding theimpact ofthis transient onthe Instrument Nitrogen System andInstrument AirSystem?
A. Instrument air will backup the 'A' Instrument Nitrogen header tothedrywell.
B. instrument air will backup the 'B' Instrument Nitrogen header tothedrywell.
C. Instrument Nitrogen willcontinue tosupply all equipment normally.
D. Both Instrument Nitrogen headersto the drywell isolated.
Answer: B Answer ExpladationL O L '
Choice Basis orJustification Correct: B Thefollowing valves willclose fromthe listed conditions:
AO-2969A "Drywell Instr. N2isolation"(GRP II Inboard) and SV-8100 "N2Compressor SuctionValve" (GRP lil Inboard). When thesuction valve closes, both N2compressors will trip ona loss of suction. AsN2pressure lowers, instrument air will backup the N2.
However since the outletofthe'A' header ofN2is closed dueto the GRPII Inboard isolation, ony'B' header willbesupplied.
Distractors: A Plausibe if candidate confuses theresults oftheinboard vs outboard isolations. The'B' header will stillbesupplied by instrument airbecause only theoutlet ofthe'A' header hasisolated duetotheINBOARD isolations.
C Plausible if candidate fails torecallall the equipment effected bya GRPII andGRPlil isolation andthesubsequent plant responses associated with those failures.
D Plausible candidate if misinterprets theisolations aseither the inboard oroutboard isolations willcause both compressors totrip ona loss ofsuction, however onlyoneheader would belost during thehalf isolation andinstrument air would back that u Page:26of214 16March 2020
2020 NRCROExamrev0 Test ID: 330066 Question $21nfo; C AL ... . ...
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 2 Difficult: 2.00 .
S stemID: 993007 User-Defined ID: ILT-5016-6E-002 Cross Reference Number: 300000 K 6.07 To ic: ILT-5016-6e-002 Electrical Transient Inboard G II/III NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes High 10CRF55.41(b)(
7 Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other Exam Bank X ILTExamBank Reference s: PLOT-5016, COLGP-8.C Learning PLOT-5016-6E Ob'ective:
K/ASystem:300000 -
Instrument Air Importance:
RO/SRO 2.5/2.6 K/A K6.07Knowledge oftheeffect thata loss Statement:ormalfunction ofthe following have will on theInstrument Air:Valves REQUIRED None MATERIALS:
Notes and Comments:
Page: 27of214 16March2020
2020NRCROExamrev0 Test ID: 330066
. . / / f J Unit a refueling outagewith 2isexiting ModeSwitch inSTARTUP withthe conditions:
following D WRNMhasbeen bypassed using bypass joystick duetofailingINOP While continuing the startupthe following occurs:
H WRNMfails INOP (1)
Whatalarm would beexpected with this condition?
AND If (2) theHWRNMwereplaced inbypass using bypass joystick, wouldthat reset?
alarm A. (1) ARC210G-3"AWRNMTRIP/INOP" (2) YES B. (1) ARC210G-3"AWRNMTRIP/INOP" (2) NO C. (1) ARC210H-3"BWRNMTRIP/INOP" (2) YES D. (1) ARC210H-3"BWRNMTRIP/lNOP" (2) NO Answer: D Page: 28of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Choice BasisorJustification Correct: D The'B' WRNMTRIP/lNOP alarm would comeinasthe HWRNM ispart ofthe'B' WRNMchannel. Thebypass isajoystick switch that canonly bypass oneWRNMina channel atatime.Sincethe
'D' WRNM(also inthe channel)
'B' isalready bypassed as indicated inthe stem, whenthe 'H' WRNMisplaced inbypassthe
'D'WRNM would nolonger bebypassed andwould completethe logic for the alarm tobein. Therefore thealarm wouldnotbeable Distractors: A F p plaushe asthere are Motal WRNMwith 4 WRNM~ on the 'A'channel and4 onthe 'B' channel. Thecandidate may misinterpret which WRNM isonwhich channel.
Second part is plausible because iftheWRNMwith thefailure can bebypassed and there is noother WRNMbringing inthealarm, the alarm wouldclear.
B First part isplausible as there are8total WRNMwith 4 WRNMon the 'A' channel and4 on the 'B' channel. Thecandidate may misinterpret which WRNM is onwhichchannel.
Plausible ifcandidate also misinterprets what channelthe'D' WRNMison.
C First part iscorrect.
Second part isplausible if candidate misinterprets theability to bypass more than oneWRNMoneither channel.
Page: 29of214 2020 16March
2020NRCROExamrev0 Test ID: 330066 Question 13Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2123564 User-Defined ID: ILT-5060C-9K4-001 Cross Reference Number: 215003 A1.06 To ic: ILT-5060C-9k4-001 B assin multi leWRNM NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes High 10CRF55.41(b)(
5 Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other Exam Bank ILTExamBank Reference s : PLOT-5060C, ARC210G-3,H-3 Learning PLOT-5060C-9k4 Ob'ective:
K/ASystem: 215003Intermediate Importance:
Range Monitor (IRM) RO/SRO S stem 3.3/ 3.2 K/A A1.06Ability topredict and/or monitor Statement:changes inparameters associated with operating theIntermediate Range Monitor (IRM) System controlsincluding: Lights and alarms REQUIRED None MATERIALS:
Notes and None Comments:
Page: 30of214 16March 2020
2020 NRCROExamrev0 Test ID: 330066 Thesitehasexperienced a Loss ofOffsite Power with the conditions:
Following e E2,E3,andE4Diesels cannot bestarted a SE-11ATTK"Backfeeding Safe Shutdown loads usingE1Diesel isinprogress Generator" All steps toenergizing prior theE-12 Bus are complete.
a The"E-12 BKR"control switch istaken toclose Which oneofthe followingdescribes the expected status of the E124Load Center ESWpump and'A' 30secondslater, with noadditional operator action?
A. TheE124LoadCenter isNOTenergized The'A' ESWpumpisNOTrunning B. TheE124Load center isenergized The'A' ESWpumpisrunning C. TheE124Loadcenter isenergized ONLY D. The'A' ESWpumpisrunning ONLY Answer: C Page: 31of214 16March 2020
2020 NRCROExamrevo Test ID: 330066 Choice BasisorJustification Correct: C TheE124Load center will automatically closeontheE-12 Bus approximately3 seconds after power issuppliedtothebus.The
'A'ESWpumpwill not berunning immediately asfurther backfeeding steps mustbetaken inorder tobackfeedthe ESW
'A' pump. Once backfed the 'A'ESWpumpwill ultimately start, receiving power throughthe E-12 bus.
Distractors: A Plausible asmany breakers are taken toopenduringbackfeeding operations andthe candidate maymisinterpret theE124Load Center Breaker being taken tooff. The'A' ESWpumpwill notbe running.
B TheE124 Load center will beenergized, howeverthe'A'ESW pumpwill not be running. Plausible since the ESWpumpis
'A' needed urgently in order tocool the diesel which generator currently hasnocooling andthe candidate maymisinterpret the power supply tothe 'A' ESW pump, asit bythe issupplied E-22 busandwould need to be backfed first.
D Plausible asmanybreakers are takentoopen duringbackfeeding operations andthe candidate may misinterpret theE124Load Center Breaker being taken to open.
Plausible since the'A' ESWpump is needed urgently inorder to cool the diesel generator which currently hasnocoolingandthe candidate maymisinterpret the powersupply tothe 'A'ESWpump, asit issupplied bythe E-22 busandwould need tobebackfed first.
Page: 32of214 16March 2020
2020 NRCROExamrevo Test ID: 330066 Questionl4 info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 3 Difficul : 3.00 S stemID: 2123579 User-Defined ID: ILT-5054-9K2-001 Cross Reference Number: 262001 A1.02 To ic: ILT-5054-9k2-001 Backfeedinfrom E12bus NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes High 10CRF55.41(b)(
5 Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other Exam Bank ILTExamBank Reference s: SE-11 attachment K Learning PLOT-5054 Ob'ective:
K/ASystem: 262001 -
A.C. Electrical Importance:
Distribution RO/SRO 3.1/ 3.5 K/A A1.06Ability topredict and/or monitor Statement: changes inparameters associated with operating the A.C. Electrical Distribution controls including: Effects ofloads when enerizin a bus REQUIRED None MATERIALS:
Notes and This question meets theK/Aasthe Comments: candidate would bemonitoring the change ofthebusduetoloads being automatically/
manually added whenfirst re-energizing the bus.
Page: 33of214 16March2020
2020NRCROExamrev0 Test 330066 ID:
$$AW$k3$jj pkf$ffi giffifi gy$$W(fff(ffi $Q$(($fjj%$$2 pyf&Fk M$fffffffjgffkfffif))j@j ig $fA$4 Unit2isexperiencing a LossofCoolant Accident withthefollowingconditions:
= T-111"Level Restoration" iscurrentlyinprogress
= A,B,CandD Core Spray pumps arerunning
= A andB Core Spray loop flows are indicating approximatelyOgpm
= Noother ECCSpumps are available
= T-112"Emergency Blowdown" isbeingperformed
= Reactor Vessel level is210inches andlowering
= Reactor Pressure is480psig andlowering T-111 nextstep calls to"Maximize RPVinjection UsingAllSystems andSubsystems" Which oneofthe following:
- 1) Describe the required operator action AND
- 2) Theearliest CSflow tothe reactor isverified A. 1)Immediately open the Core SprayMO-2-14-12A(B) "InboardDisch" Valves 2)Verify Core Spray first shows flowatapproximately305psig reactor vessel pressure B. 1)Verify the Core Spray MO-2-14-12A(B) "Inboard Disch" Valves automatically open at appropriate pressure
- 2) Verify Core Spray first shows flowatapproximately305psigreactor vessel pressure C. 1)Immediately open theCoreSpray MO-2-14-12A(B) "InboardDisch" Valves
- 2) Verify Core Spray first shows flowatapproximately330psig reactor vessel pressure D. 1)Verify theCore Spray MO-2-14-12A(B) "Inboard Valves Disch" automatically open at appropriate pressure
- 2) Verify Core Spray first shows flowatapproximately330psig reactor vessel pressure Answer: D 34of214 Page: 16March 2020
w ::
2020 NRCROExamrevo Test ID: 330066 Choice Basis orJustification Correct: D TheCore Spray inboard discharge valve hasanautomatic open signal at450psig reactor vessel pressure. TheCore Spraypumps arecurrently aligned toinject with the exception oftheinboard discharge valve. Theoperator isexpected toverifythis automatic actionandonly open the valve whenthe automatic action didnot occur. TheCore Spray shutoff headisapproximately 330psigin the reactor vessel.
Distractors: A Plausible if candidatemisinterprets thesteps inmaximizingRPV injection andlines upfor injection before automatic actions occur.
Manyactions in the plant are taken manually beforetheautomatic actionsoccur andthe candidate mayconfuse them.
Second part is plausible asthe Shutoff head ofthe RHRsystem is approximately 305 psigreactor vessel pressure andthecandidate mayconfuse the two. CoreSpray should showing start injection around 330psig.
B Thefirst part iscorrect.
Second part isplausibleas the Shutoff head oftheRHRsystem is approximately 305psig reactor vessel pressure andthecandidate mayconfuse the two. Core Spray should start showing injection around 330psi,q.
C Plausible ifcandidate misinterpretsthe steps inmaximizingRPV injection andlines upfor injection before automatic actions occur.
Manyactions intheplant aretaken manually before theautomatic actions occur andthe candidate mayconfuse them.
Second art iscorrect Page: 35of214 16March 2020
- x n =
x 2020NRCROExamrev0 Test ID: 330066 Question15 Info' T .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 3 Difficult: 2.00 S stemID: 2123587 User-Defined ID: ILT-5014-10F-001 Cross Reference Number: 209001 A2.06 To ic: ILT-5014-10f-001 CSin'ection valve not o en NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes High 3 10CRF55.41(b)(
5 Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other Exam Bank ILTExamBank Reference s : T-111 Bases Learning PLOT-5014 Ob'ective:
K/ASystem: 209001Lowpressure Importance:
Core Spray System RO/SRO 3.2/
3.2 K/A A2.06Ability Statement:thefollowing (a) to predict ontheLowPressure theimpactsof Core Spray System; and(b) based onthose predictions, useprocedures tocorrect, control, ormitigate theconsequences of those abnormal conditions oroperations:
Inade uate s stemflow REQUIRED None MATERIALS:
Notes and None Comments:
Page: 36of214 16March 2020
n =
o 2020NRCROExamrev0 Test ID: 330066
. :' '. / /
3isat100%power withthe Unit followingconditions:
= E134-T-B hasbeen de-energized toperform buswork Thenext shift, the followingalarms arereceived:
= ARC320F-5"Inverter Trouble"
= ARC320G-5"Inverter DCsupplyUndervoltage"
= Noother alarms are received Which ofthe following, if any, will beentered tomitigate theevent?
A. ON-112-3 "Loss ACPower" ONLY ofUninterruptible B. SE-13 "Loss ofa 125or250VDCSafety Related Bus"ONLY C. ON-112-3 "Loss ACPower" ofUninterruptible AND SE-13 "Loss ofa 125or250VDCSafety Related Bus" D. NEITHER ON-112-3 "LossofUninterruptible ACPower" NOR SE-13 "Loss ofa 125or250VDCSafety Related Bus" Answer: A Page: 37of214 2020 16March
l 2020NRCROExamrev0 Test ID: 330066 Choice Basis orJustification Correct: A Duetotheloss ofthe DCpower supply tothe theinverter inverter, loses power. The Static switch would switch tothea lternate source, however the alternate source isE134-T-B which hasbeen de-energized. This leads toa loss ofthe Uninterruptible power supply andON-112-3would beentered Distractors: B Plausible asthe inverter DCsupply isa250VDCbusandthe candidate maymisinterpret thisasaSafety Related busasit is supplying uninterruptible power andmayenter SE-13. Inaddition the inverter DCsupply isconnected upstream to3BD18 Distribution panel that supplies a250VDCSafety Related bus.
Thecandidate mayalso misinterpret the power suppliestothe Uninterruptible AC powerandnotcorrectly diagnose that the Alternate power supply is already de-energized.
C Plausible ifthecandidate misinterprets the faultbeing further upstream of the I nverter DC supply, which is connected tothe 3BD18Distribution panel that supplies a 250 VDCSafety Related bus. It fhe 3BD18Distribution panel wasde-energized inthis scenario, both procedureswould beentered.
--.DPlausible asthe candidate may misinterpret thepower suppliesto the Uninterruptible ACpower and not correctly diagnose thatthe Alternate power supply isalready de-energized.
Notenterin SE-13 would becorrect Page: 38of214 16March 2020
.= =
u 2020NRCROExamrev0 Test ID: 330066 Question46 lefo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 3 Difficult: 2.00 S stemID: 2123766 User-Defined ID: ILT-5058-10A Cross Reference Number: 262002 A2.01 To ic: ILT-5058-10a Lowvolta eUPS NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes High 3 10CRF55.41(b)(
5 Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other Exam Bank ILTExamBank Reference s : E-27, E-29, SE-13, ON-112-3, AO 56E.2-3 Learning PLOT-5058-10a Ob'ective:
K/ASystem:262002Uninterruptible Importance:
Power Supply RO/SRO 3.2/ 3.2 K/A A2.01Ability to(a) predict theimpacts of Statement:thefollowing ontheUninterruptible Power Supply; and(b) based onthose predictions, useprocedures tocorrect, control, or mitigate theconsequences ofthose abnormal conditions oroperations:
Undervolta e REQUIRED None MATERIALS:
Notes and None Comments:
Page: 39of214 16March 2020
e 3
2020 NRCROExamrev0 Test ID:330066
/ ,
2 HPCIis Unit injecting into the RPVfollowing aGroup Iisolation.
Thefollowingconditions exist:
= HPCI steam pipingarea temperature is210degrees F andrising
= RPVlevel is-100 inchesand rising slowly
= Drywell pressure is1psig andsteady
= HPCI pumpdischarge flowonFl-2-23-108 is5000 gpmandsteady Basedonthe above conditions, theHPCIPCIS Group IV isolation A. will occur if/when HPCIarea temperature reaches 250degrees F.
B. occur will if/when RPVlevel risesabove +45inches.
C. hasfailed. Close valve MO-2-23-15 "HPCI SteamIsolation". Thebreaker for MO-2-23-15 "HPCI Steam Isolation"canremain closed.
D. hasfailed. Close valve MO-2-23-15 "HPCI Steam Isolation". The breaker for MO-2-23-15 "HPCI Steam Isolation"mustbeopened.
Answer: D Answer Explanation Choice Basis orJustification Correct: D HPCI should have isolated.Thearea temperature isabove theisolation setpoint of200degrees F.Thereason that C iswrong andD iscorrect is because with a failedisolation signal theisolation valvewillnot stayclosed with aninitiation signalpresent. Whenthe valve reaches thefullclosed position the valve willcomeopen automatically because oftheinitiation signal (-100"). Theonly waytostop thevalve from coming openisto remove theelectrical feed.
Distracter A Theisolation setpoint is200degrees F.Plausible ifthecandidate s: misinterprets theHPCIisolation setpoint with theReactor Building Main Steam Line isolationsetpoint.
B Thehigh RPVlevel triplogic(+45) signal does not affecttheisolation setpoint. Plausible the if candidate misinterprets the ofthe relationship high RPVlevel trip logicandtheisolation logic.
C MO-15 will not stay closed with the initiation signal present (5-48inches RPVlevel) andtheisolation signal failed. Plausible if the candidate misinter rets howtheinitiation sinal affects theMO-15 valve loic.
Page: 40of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Question 17Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 1.00 S stemID: 1137055 User-Defined ID:
Cross Reference Number: 223002 A3.01 To ic: ILT-5007G-51-002 NumField 1:
NumField 2:
Text Field:
Comments: Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes HIGH 10CRF55.41 b7 Source Documentation Source: NewExamitem Previous 2 NRC Exams Modified Bank Other ExamBank X ILTExamBank (2114067)
Reference(s): GP-8.F PCISIsolation -
Groups IVand IV-B,COLGP-8.F-Groups IV,and IV-B Isolation,M-1-S-23, M-1-S-36 Learning PLOT-5007G.51 Ob^ective:
K/ASystem: 223002 Primary Importance:
Containment Isolation RO/SRO System/Nuclear Steam 3.5/ 3.5 Su I Shut-off K/AStatement: A3.01Ability tomonitor automatic operations ofthePRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAMSUPPLY SHUT-OFF includin :Valve closures REQUIRED None MATERIALS:
Notes and None Comments:
Page: 41of214 16March2020
ow :: '.
PSSW 2020NRCROExamrev0 Test ID: 330066 W$@f .
- !%it, $jjirj?$ji;y VWWfffffjkgiffMiffjjj$ifffj)QW$thi L'?$jkfTf5ffJiig[
41),iffffjompippam 2isat85%power Unit withthe following conditions:
= All RFP's arein automatic Thefollowing occurs:
= "RFPA FLOW"ontheDigital Feedwater Control System fails upscale nstantaneously DFWCAlarm isdisplaying "FCS-RFPAFLOW-AA" Whichoneofthefollowing identifies theexpected response ofthe"A"RFPandtheDigital Feedwater System?
Control A. (1) "A" RFPspeed lowers (2) D FWC swaps t omanual B. (1) "A" RFPspeed remains constant (2) DFWCswaps tomanual C. (1) "A" RFPspeed lowers (2) DFWCremains inautomatic, but swaps tosingle element control D. (1) "A"RFPspeed remains constant (2) D FWC remains inautomatic, but swaps tosingle element control Answer: D Page: 42of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Choice BasisorJustification Correct: D Whenthe Feed flow indication the for 'A' Reactor feedpump (in fails this case upscale) the feedwater Digital system detects the failure andremoves the failed point. Thelast known 'GOOD' value isused for FWflow total interlocks. TheDFWCwould stayin automatic buts wap tosingleelement control because not allFlow elements areknown asgood.
A First part is Distractors: plausible if the candidate misinterprets DFWCresponse toan instantaneous failureofflow. the If flow failed slowly, theDFWCsystem would follow the flow untilitreaches adetermined failure pointatwhichtime theDFWCwould disregard the 'BAD' signal. During this timetheRFP speed could lower. However with aninstantaneous failure theDFWCwould immediately dismiss the data pointas'BAD' andremove fromits calculations.
Second part isplausible as DFWC system does swap tomanual during certain failure criteria,however afailureofa flow indicator alonedoesnot meetthis criteria.
B First part iscorrect Second part isplausible asDFWC system does swap tomanual during certain failure criteria,however afailure ofaflow indicator alonedoes not meetthis criteria.
C First part isplausible ifthe candidate misinterprets DFWC response toan instantaneous failure offlow. If the flow failedslowly, the DFWCsystem would follow theflow untilitreaches a determined failure point atwhichtime theDFWCwould disregard the'BAD' signal. During this time theRFP speed could lower. However with aninstantaneous failure the DFWCwould immediately dismiss thedata pointas'BAD' andremovefrom its calculations.
Secondart iscorrect.
Page: 43of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Question 18Info Question T e: Multi IeChoice Status: Active Alwasselect on test? No Authorized forractice? No Points: 1.00 Time toCom lete: 0 Difficult: 1.00 S stem ID: 2131290 User-Defined ID: ILT-5006-5T-004 Cross Reference Number: 259002 A3.04 To ic: lLT-5006-5t-004 NumField 1:
NumField 2:
Text Field:
Comments: Ps chometrics Level of Difficulty Time RO Knowledg Allowance e minutes HIGH 10CRF55.41 b7 Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other ExamBank X ILT ExamBank Reference s : SO6D.7.E-2 Learning PLOT5006-5t-001 Ob'ective:
K/ASystem: 259002Reactor -
Water Importance:
level Control System RO/SRO 3.2 3.2/
K/AStatement: A3.04Ability tomonitor automatic operations ofthe REACTOR WATER LEVELCONTROL SYSTEM including:
Chanesinreactor feedwater flow REQUIRED None MATERIALS:
Notes and None Comments:
Page: 44of214 16March2020
2020NRCROExamrev0 Test ID: 330066 thA%ddimd6Tf$37$f&W$hfffkhf[ff))$$WWhkdff$W81AWitlifD$
Unit 2andUnit 3are at100% power whenthefollowing occurs:
Lossofoffsite power DrywellpressureinUnit 2 is2.6psig andrising slowly DrywellpressureinUnit3 is 1.5psig andrising slowly E1andE4Diesel Generators are running.
NODiesel Generator coolingwater is available.
Based onthe above conditions, whichaction below isrequired toshutdown theE1andE4Diesels in accordance with SE-11, "Loss ofOffsite Power"?
A. Direct theEOtodepress the'red buttons' totrip the fuel racks.
B. Place theDGcontrol switches tothe 'Pull-To-Lock' position.
C. Pullthe 4KVfeeder breaker fuse blocksto remove the startsignal.
D. Installelectrical jumpers toinsert DGdifferential lockout.
Answer: D Answer Explanation e . . .. xnd . . . . C A C . . . .. .... ... . .
Choice Basis orJustification Correct: D During anSE-H itfhe diesels arerunning without coohng water, ATT'A' isperformed. This installs jumpers thatbypasses the diesel MCAstart andrun signal. TheMCAsignal hasthe diesel runfor 10minutes without anyjacket coolanttemperature trips.
TheMCAsignal also bypasses thecontrol roomswitch and maintains the diesel running for 10minutes. Performing this procedure allows thecontrol room totake control ofthe diesel and DisFaWs': the di'esel A P a this would cause tobeshutdown, however this would not allow control from thecontrol roomfor arestart and isnotdirected bySE-11.
B Plausible asthis would shutdown adiesel andprevent itsrestart, except intheevent ofa MCAsignal. Which isstated inthestem asDrywell pressure being > 2 psig onUnit2.This would start a diesel inPTLandwould not allow it tobeshutdown.
C Plausible aspulling the 4KVfeeder breakerfuse blocks isa section within SE-11 that will beused whenbackfeeding power tothe cooling water pumps. However these fuseblocks will not affect the startofthe diesel andthe candidate mymisinterpret the useof these fuse blocks.
Page: 45of214 16March 2020
2020 NRCROExamrev0 Test ID: 330066 Question'19lofo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 3 Difficult: 2.00 S stemID: 994047 User-Defined ID: ILT-1555-3-013 Cross Reference Number: 264000 A4.03 To ic: ILT-1555-013 SE-11 DGshutdown with nocoolin water NumField 1: 6865 NumField 2: NA Text Field: B Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes Memory 10CRF55.41(b)(
7 Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other Exam Bank X ILT ExamBank Reference(s): SE-11 Learning PLOT-1555-3 Ob'ective:
K/ASystem:264000Emergency Importance:
Generators (Diesel/Jet) RO/SRO 3.2/
3.4 K/A A4.03Ability tomanually operate and/or Statement:monitor inthe control room: Transferof emergency controls between manual and automatic REQUIRED None MATERIALS:
Notes and This question isa K/Amatch because it is Comments: asking themanual actions that need tobe taken inorder totransfer the controlofthe Diesel Generator back tothe controlroom from the automatic control created bythe MCAsinal.
Page: 46of214 16March2020
x Sey =
2020NRCROExamrev0 Test ID: 330066 Wh33ADVD8@WW4lWAffiMk(rd)1DhP))A%Di A LOCAoccurred on Unit 2 RHRwasplaced inDrywell Sprays, withthe following conditions noted:
a Drywell Pressure: 15psig a RPVLevel: -50inches e RPVPressure: 600psig 10Minutes later,the following conditions exist:
a Drywell Pressure: 10psig a RPVLevel: -180inches a RPVPressure: 400psig Which oneofthe following statements correctly describes the expected responseofRHR?
A. Drywell Sprays automatically will secure.
RHRjnjection valves willNOTautomatically lineup to inject.
B. Drywell Sprays automatically will secure.
RHRinjection valves willautomatically lineuptoinject.
C. ThePROmustmanually secure Drywell Sprays.
RHRinjection valves willNOTautomatically lineup toinject.
D. ThePROmustmanually secure Drywell Sprays.
RHRinjection valves willautomatically lineuptoinject.
Answer: D AnswerExplanationnnnCA C '. .
n A. .
Choice Basis orJustification Correct:D T-204 directs the spray valves beclosed upon receiptofa LOCAsignal because the spray valves donotreceive anautomatic closed signal under these conditions.
Distractors A Plausible ifthe candidate doesnotunderstand thatthe spray valves will not close because thecontainment spray overridekeyhasbeenused.
Plausible ifthecandidate doesnotbelieve theinitiationsignal will openthe in'ectionvalve because the containment s ra override ke hasbeenused.
B Plausible ifthe candidate doesnotunderstand thatthe spray valves will not close because the containment s raoverride ke hasbeen used.
C Plausible ifthe candidate doesnotbelieve theinitiation open will signal the in'ectionvalve because the containment s raoverride ke hasbeenused.
Page: 47of214 16March 2020
2020NRCROExamrev0 Test ID: 330066
/
Question201nfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 3 Difficult: 2.00 S stemID: 993898 User-Defined ID: B NRC 2019 Cross Reference Number: 203000 A4.02 To ic: ILT-5010-5d-002 D ell S raValve Status ostLOCA NumField 1:
NumField 2:
Text Field:
Comments:
Psychometrics Level of Difficulty Time RO Knowledge Allowance (minutes)
High 2 3 10CRF55.41(b) 10 Source Documentation Source: NewExamitemX Previous NRC Exam(2019)
Modified Bank Other Exam Bank X ILT ExamBank (446781)
Reference(s): T-204 notes, M-1-S-65 Learning ILT-5010-5d Objective:
K/A System: 203000RHR/LPCI:
Importance; RO /
Injection Mode SRO 4.1
/4.1 K/A A4.02Ability tomanually operate and/or Statement:monitor inthecontrol room:System Valves REQUIRED None MATERIALS:
Notes and None Comments:
Page: 48of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 40%$hiff$$Q$$Q$bj$yjjfA$$%ffQj jf($j)f$j
$f$($$$i ykQf ff$%f[$f(i$$Wj ritif@yjpfjjrge; Unit2isexperiencing anATWS. Plant parameters areasfollows:
= Reactor power is cycling between 34%power and38%power onthe APRMrecorders.
= 40Control Rodsare atposition 48. Their associated blue SCRAM lightsontheFull Core Display areNOTlit.
= TheMain Turbine ison-line at~450 MWe.
Inaccordance with T-101 "RPVControl" which oneofthe following actions mustbeperformed atthis time?
A. TriptheMain Turbine B. Trip both Recirc Pumpssimultaneously C. Perform T-213-2 "Scram Solenoid Deenergization" D. Perform T-216-2 "ControlRodInsertion by Manual ScramorIndividual Scram Test Switches" Answer: C A AmAA C Answer Explanatione e .
Choice Basis orJustification Correct: C The40rods remaining atfull outposition areexperiencing an electrical ATWSasindicated bythe blue SCRAM lights notbeing lit.
Inaccordance with T-101, during anElectrical ATWS T-213 is performed inorder toremove power from thesolenoid valves to SCRAM therods.
Distractors: A Plausible astripping theMain Turbine isperformed during most transients andiscalled tobeperformed inthe PROScram actions.
However trippingoftheturbine should occur around 50MWeand theturbine iscurrentlyaround450 MWe.
B Plausible astripping theRecirc Pumpsispart ofanATWSstrategy andwould beperformed during this scenario, however thedirection istotrip theRecirc Pumps10seconds apart andnot simulaneously D Plausible asthis isanother ATWSstrategy usedinT-101, however thisstrategy isused during a hydraulicATWS.Therods that are outdonothave their blue SCRAMlights indicating lit, that they are ex eriencin a electrical ATWS.
Page:49of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Question 2tinfo' . . ,
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 3 Difficult: 2.00 S stemID: 993894 User-Defined ID: ILT-2101-1-008 Cross Reference Number: 212000 2.4.6 To ic: ILT-PBIG2101-008 Actions forATWSandT-213 NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes High 10CRF55.41(b)(
7 Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other Exam Bank X ILTExamBank Reference(s): T-101 Learning PLOT-2101-1 Obective:
K/ASystem: 212000Reactor -
Importance:
Protection System RO/SRO 3.7/ 4.7 K/A 2.4.6Knowledge ofEOPmitigation Statement:strate ies REQUIRED None MATERIALS:
Notes and This question isa K/Amatch because it is Comments: asking what action outofanEOPwould help mitigate anelectrical failure ofpart of RPS.
Page: 50of214 16March 2020
Ae 2020NRCROExamrevo Test ID:
330066 ADD&W$dfff!fdikififffh%/iWMff$%Wf/////%Mffff/fdAM$Mf#3332 Whichofthe following istrue regardingDCpower tothe supplies DieselGenerators:
2 DCdistributionsupplies power Unit toDieselGeneratorsA AND 3 DCdistribution Unit power toDieselGeneratorsJ21 supplies A. 1) E1andE2 2)E3andE4 B. 1)E3andE4 2)E1andE2 C. 1)E1andE3 2)E2andE4 D. 1) E2andE4 2)E1andE3 Answer: A Answer Explanation%A A;jn;TWn;A AxC T Ae Choice BasisorJustification Correct: A FeedsarelocatedonprintsE-26andE-27 withUnit 2 panels 20D21and20D22 goingtoE1andE2respectively and Unit 3 30D23 panels and30D24 goingtoE3andE4respectively.
Distractors: B Plausible asthedieselsareseparatedthiswayfor DCdistribution, howeverthecandidatemaymisinterpretwhat feed comes from whatunit.
C asmostECCSsystems Plausible arecategorized with A andC being togetherandpowered bytheE1andE3diesels. Thesame for istrue B andD beingpoweredfrom E2andE4.Thecandidate
........-.maymisapply logic this totheDCdistributionfortheDieseIs D asmostECCSsystems Plausible arecategorized with A andC being togetherandpowered bythe E1andE3diesels. Thesame for istrue B andD beingpowered from E2andE4.Thecandidate maymisapply logic this totheDCdistributionfortheDiesels and misinter retwhatfeedcomesfrom what unit.
Page:51of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Question 22sinfo C Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoCom lete: 0 Difficult: 0.00 S stemID: 2124000 User-Defined ID: ILT-5057-12 Cross Reference Number: 263000 2.2.3 To ic: ILT-5057-12 DCdistribution todiesels NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes Memory 10CRF55.41(b)(
7 Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other ExamBank ILTExamBank Reference(s): PLOT-5052, E-26 sht1, E-27 sht1 Learning PLOT-5057-12 Ob'ective:
K/ASystem: 263000DCElectrical Importance:
Distribution RO/SRO 3.8/ 3.9 K/A 2.2.3 -
(multi-unitlicense) Knowledge ofthe Statement:design, procedural, andoperational differences between units.
REQUIRED None MATERIALS:
Notes and This question meets theK/Abecause the Comments: lineup oftheDCdistribution isa design difference between the 2 units ofwhat common e uimentthe ower.
Page: 52of214 16March 2020
j 2020NRCROExamrev0 Test ID:
330066 42%$W$2862%dkWf%$WAfA($i$ii$$60$Ai$f/fjiid$2$#$ilk$$4 A small-break LOCA occurred onUnit 2.
T-112"Emergency Blowdown" isinprogress with 5ADSSafety all Relief Valvesopen.
Current plant conditions are as follows:
= RPVpressure is380psig
= Drywell pressure is10psig
= AllECCSpumps arerunning Basedonthese conditions, MO-2-10-25B "RHRInboard Valve" is (1)
AND AO-2-10-46B "Testable Check Valve" is (2)
A. (1)open (2)open B. (1)closed (2)open C. (1)open (2)closed D. (1)closed (2)closed Answer: C Answer E5ianationTA A :A:At:;:A CA n . A2 Choice Basis orJustification Correct: C M'O-25 opens at450psig', but 380ps'ig"is above't'he shuto'ff headof theRHRpumps, andtherefore thetestable check valve isclosed.
Distracters: A Part 1iscorrect Plausible if candidate misinterprets thepressure inwhich a discharge path iscreated andthe discharge headofthepumps.
B Plausible if thecandidate misinterprets ofthevalves, thelineup and that thetestable check before discharge, andcould misinterpret that the minflow isinthis flow path resulting inthecheck valve opening andwhentheRHRinboard valve will automatically open.
Part 2 iscorrect Page: 53of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Question 23Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 2.00 S stemID: 995356 User-Defined ID: B CERT Cross Reference Number: 203000 A3.08 To ic: ILT 5010-002 NumField 1:
NumField 2: A CERT Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance (minutes)
HIGH 10CRF55.
41b 8 Source Documentation Source: NewExamItem C Previous NRC Exam:()
C Modified BankItem COther Exam Bank: ()
2 ILT Exam Bank Referenc M-361; T-101 s)
Objective K/A" 203000 RHR/LPCI: Importance:
RO/
System:Injection Mode SRO 4.1/
4.1 K/AStatement:
A3.08Ability tomonitor automatic ofthe operations RHR/LPCI: Injection Modeincluding :Systeminitiation seuence REQUIRED NONE MATERIALS: ........... ....... ..... .-..-.-.-...------...--...-----...... .-....... ...... . . .
Notes and Comments:
Page: 54of214 16March 2020
A 2020NRCROExamrev0 Test ID: 330066 fj$h$f$jMl@$k$@#2%fd@WMAAWffWff#/R@$F2FAM%$$2 Unit2isoperating at 70% power atthe endofcycle with the followingconditions:
= APRMchannels are in-service andoperable All
= APRM'1' hasatotalof 13 LPRM detectors bypassed
= APRM'1' has7 out ofa possible 10'B' level LPRMdetectors bypassed Based onthese conditions, which APRM '1' responseis correctifanadditional 'B'levelLPRMtoAPRM'1' ismanuallybypassed?
A. NOalarms andNORod Block B. AnAPRMTROUBLE alarm and Rod Block C. AnAPRMDOWNSCALE alarm and Rod Block D. AnAPRMINOPalarm, RodBlock andScram VotetoRPS Answer: B Answer Explanations Correct: B APRMtrouble LPRMsper alarm androdblock APRMwill due to"too fewinputs"(< 3 level). continueto average the remaining LPRMs.
Distractors: A Plausible asthe total LPRMsarestill greaterthan the"too fewinputs" per a 'B' APRMsetpoint level places
(< 20LPRMs
< 3 LPRMs total),
onthat however since the removal analarm and rodblock level, of is enerated C Plausible astheLPRM's feed the into APRMaverage and would cause adownscale alarm ifenough LPRM's failedlow,however 30 LPRMsremaining at70%power will notresult inanAPRM downscale trip.
D Conditions result inatrouble alarm only,NOTanINOP trip with the GE NUMACAPRMsystem. Plausiblesince standard BWRAPRM system generates anINOPtrip ontoofewinputs.
Page: 55of214 16March 2020
n 2020NRCROExamrev0 Test ID: 330066 Question 24Infio Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 3 Difficult: 2.00 S stemID: 994752 User-Defined ID: ILT-5060-7D-002 Cross Reference Number: 215005 K5.01 Topic:
. ILT-5060-7D-002 Unit 2isoperating at70%power atthe endof c clewith thefollowin conditions:
NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes Memory 3 10CRF55.41(b)(
5 Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other Exam Bank X ILTExamBank Reference(s):A-3, ARC-211 ARC-211 C-2, ARC-211 E-5, Tech S ec3.3.1.1 Bases Learning PLOT-5060-7D Ob'ective:
K/ASystem:215005APRM/LPRM -
Importance:
System RO/SRO 2.8/2.9 K/A K5.01Knowledge oftheoperational Statement:implications ofthefollowing concepts as they apply toAPRM/LPRMSystem:
LPRMdetector o eration REQUIRED None MATERIALS:
Notes and Comments:
Page: 56of214 16March 2020
,,n; 2020NRCROExamrev0 Test ID: 330066 Wd$D@$$$d%Wildd$ff$1Eh1l41hd3W$12f@hd Unit 2isperforming astartup using GP-2-2 "Normal Plant Start-up"
= SO6C.1.A-2 '"C'Reactor Feedwater PumpStartup with Vessel Control Level Through Established AO-8091" isinprogress a 'C'RFPis inmanual control with MO-2149C "CDischarge" CLOSED Theprocedure statesthat while raising Reactor power, adjust RFPTspeed AO-8091 tomaintain "start-up level controller"between 30and70%.
WhileratsingReactor power, AO-8091 would be expected to--(1)--
AND Inordertomaintain AO-8091 within bandthe 'C' RFPT speed mustbe-(2)
A. 1)OPEN 2)RAISED B. 1)CLOSE 2)RAISED C. 1)OPEN 2)LOWERED D. 1)CLOSE 2)LOWERED Answer: A Page: 57of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Choice Basis orJustification Correct: A While raising Reactor Power, more steam flow begenerated will causing level tolower. This will inturn cause the AO-8091 toopen further toallow morewater toflow tothe reactor. Inorder tomaintain AO-8091initsband, there must bemoredifferential pressure acrossthevalve more sothat flow can passthrough asmaller opening. TheRFPspeed creating isincreased, more differential pressure across AO-8091 more allowing toflow water through, this causes AO-8091 toclose andbemaintained 30to70%
inits band.
Distractors:B Plausible if candidate misinterprets lineup oftheAO-8091 inSO aslater 6C.1.A-2 you are monitoring for AO-8091 togoclosedasyouare valving in MO-2149C Second art iscorrect.
C First part iscorrect Plausible ifcandidatemisinterprets the responseofAO-8091toa lowering RFPflow.
D Plausible ifcandidate misinterprets lineupoftheAO-8091 inSO aslater 6C.1.A-2 youaremonitoring for AO-8091 togoclosedasyouarevalving in MO-2149C Plausible asthis would betheproper response if AO-8091 wasgoingclosed, however AO-8091 would beo eninwhile raisin ower.
Page: 58of214 16March 2020
2020NRCROExamrevo TestID: 330066 Question 25Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toCom lete: 0 Difficult: 0.00 S stemID: 2130790 User-Defined ID: PLOT-5006-9K9 Cross Reference Number: 259002 A1.05 To ic: PLOT-5006-9k9 level startu control durin startu NumField 1:
NumField 2:
Text Field:
Page: 59of214 16March 2020
j; 2020NRCROExamrev0 Test ID:330066 Comments: Vff/fAMA$WiWfiff N851A55t888 None
None P/ None P None Pschometrics Level of RO Knowledg e
HIGH 10CRF55.41 b7 Source Documentation Source: X New Exam Previous NRCExam item Modified Bank Other ExamBank ILTExam Bank Reference s : SO6C.1.A-2 Learning PLOT 50069k9 - -
Ob'ective:
K/ASystem: 259002Reactor -
Water Importance:
level Control System RO /SRO 2.9/ 2.9 K/AStatement: A1.05Ability topredict and/or monitor changes inparameters associated with operating theREACTOR WATERLEVEL CONTROL SYSTEM controls including:
FWRV/startup level controlposition:
Plant-S ecific REQUIRED None MATERIALS:
Notes and None Comments:
Page: 60of214 16March 2020
2020NRCROExamrev0 Test 330066 ID:
A2$2%d$61jji@f$$2$Wh$))))222%)2$12WWd@$WW2'$jE@$#$$339AIj$jplilliW Unit2 isat100%power whenatransient results inwater level to-10 lowering inches.
Giventhe following items 1)Control RoomVentilation fanstrip, Control RoomEmergency Ventilation fans will start.
2)Drywell vent andpurge valves receiveanisolation signal 3)Standby GasTreatmentSystem (SBGTS) filters inlet/outlet valves open andboth SBGTS fans will start.
Which ofthefollowing describe the plantresponse?
A. 1and2 ONLY B. 1and3ONLY C. 2 and3ONLY D. 1,2,and3 Answer: C A A Ase ExplanationgwUAA Answer .
L Justification: Choice Basis orJustification Correct: C A group IIIisolationwill occur at1inch RPVlevel. When a GroupIll isolation does occur, Drywell ventandpurge valves will receive an signal.
isolation Standby GasTreatment System (SBGTS) also auto aligns with fan startswith suction alignedtotheReactor Building: both SBGTS filters inletandoutlet valvesauto open andboth SBGTS fans start toensurethe Reactor Dpremains BUilding negative.
Distractors: A Plausible because other ventilation systems would tripandisolate on the1inch RPVsignal, andthecandidate maymisinterpret this isolation with theMain Control RoomVentilation isolations.
Drywell
....The vent andpurge valveswould receive anisolation.
B Plausible because other ventilation systems would tripandisolate on the1inch RPVsignal, andthe candidatemaymisinterpret this isolation with theMainControl RoomVentilation isolations.
TheSBGTsystemwould start ona 1inch RPVsignal D Plausible because other ventilation systems would tripandisolate on the1inch RPVsignal, andthe candidatemaymisinterpret this isolation with theMain Control RoomVentilation isolations.
TheDrywell vent andpurge valveswould receive anisolation.
Th Page: 61of214 16March 2020
ex; m m
)t[ @@@@f @
2020NRCROExamrev0 Test ID: 330066 infoLC E QuestionW26 .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 1 Difficult: 1.00 S stemID: 993033 User-Defined ID: ILT-5007G-1K-001 Cross Reference Number: 223002K1.12 To ic: ILT-5007G1k--001 resonse toRBvent isolation sinal NumField 1: 3013 NumField 2: NA Text Field: A Comments:
f$[(ffjpjf[ffffffyj[fjffffjj 6%$ jhiPEA None F$ffffjffff(([',TF"""([fff;jfffffffff None pMTfJTI'[T(( Eff None FMj)f(ffff(4 None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(8)
Source Documentation Source: New Modifi ILT Other Previo ed Bank Bank us2 X NRC Exams Reference(s): COLGP-8.B Learning PLOT 507G, -
4K Ob'ective:
K/ASystem:223002 Primary Importance:
Containment IsolationRO/SRO System/Nuclear Steam 3.1/3.3 Su I Shut-Off K/A K1.12 Knowledge ofthephysical Statement:connections and/or cause/effect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF andthefollowing:
Standbastreatment s stem REQUIRED None MATERIALS:
Notes and None Comments:
Page: 62of214 16March 2020
@ j 2020NRCROExamrev0 Test ID:330066 Ed0%idf2ddf#//2$ffMf$f$1WWfA@Fff//7J5FAPffailipki##4 2isat100%power Unit in normal alignmentwhenthe following occurs:
= Drywellvalve "RBCCWISOL" (MO-2-35-2374) indicates fullclosed onPanel 20C012.
Which ofthe following describesthe plant response? (Assume NOoperator actions)
A. Drywell airtemperatures will rise.
B. Control rod drive mechanism temperatures willrise.
C. Fuel Pool Cooling system temperatures will rise.
D. Reactor Recirculation Pumpsseal temperatures andmotor oil temperatures willrise.
Answer: D AnswerExplanation E ; '
Justification:Choice Basis orJustification Correct: D Unit 2wasat100%power whenvalve "RBCCW ISOL" (MO-2-35-2374) indications showed green l ight on andredlight off, meaning this normally open valvehadclosed.When closed, RBCCW flow tothe reactor recirculation Pumps islost RBCCW coolsthe recirc motor oil coolers andthe recirc pumpseal coolers, which have been impacted. With aloss ofcooling, motor oil temperatures andseal temperatures will rise,with nooperatoractions.
Distractors: A Thedrywell air iscooled bytheDrywell Chilled Water system. This cooled water ispiped inside theDrywell totheDrywell coolers.The chillers arelocated outside ofthe drywell, andthe chilled water system iscooled bythe service water system. Thusthere isnoimpact onthe ability ofthedrywell chilled water system fromcooling thedrywell air.
Theanswer isplausible since theDWCoolers arelocated inside the DW,andRBCCW canbeused asanalternate cooling system for the B Th c ntrol rocfdrive mechanisnfs areTocateci insi~de theRPVinside thedrywell. Thecontrol roddrives arecooled bythecontrol roddrive system andthus theirtemperatures arenotimpacted andwill notrise.
Theanswer isplausible since thecomponents arelocated inside the DWandare cooled bya cooling water system, but just notRBCCW.
RBCCWsupplies backup cooling totheCRDPumps.
C This answer isplausible because theFuel Pool Cooling system can useRBCCWasa backup cooling mediumthenormal -
cooling medium isservice water.
Page: 63of214 16March 2020
i;t; 2020NRCROExamrevo Test 330066 ID:
Question 27infon . .. .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: O Difficul : 0.00 . .
S stemID: 2129546 User-Defined ID:
Cross Reference Number:
Topic:
. 5f.Describe therelationships between theReactor Recirculation /Recirculation Flow Control S stem NumField 1::
NumField 2:
Text Field:
Comments:
F3f2jiEf257)AWJABRAW1/A$2jj None WJWETfW[ff$Wffffjj None Fj%%fjj(ffjjjj"W/fff) None T(M4fffjjji None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(4)
Source Documentation Source: New ModifiILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): 6280-M-316 sheet 1 Learning PLOT-5002, 5f Ob'ective:
K/ASystem:202001 Recirculation Importance:
System RO/SRO 3.1/3.2 K/A K1.07 Knowledge ofthephysical Statement:connections and/or cause/effect relationships between RECIRCULATION SYSTEM andthe following:Component coolin water s stems REQUIRED None MATERIALS:
Notes and None Comments:
Page: 64of214 16March2020
2020NRCROExamrev0 TestID:330066 e2882030" : ,;Af$MQ&&Brgh2&&A&Wjjff$El%JjE$$%jie Q $$)y$ffifffrk%f??f8iifffibig Whichofthe following lists the power supply tothe following 2 RHR"B" Unit Torus Coolingvalves:
a MO-2-10-034B, Full Flow Test a MO-2-10-039B, Torus Hdr LoadCenter..
A. E334 B. E434 C. E324 D. E424 Answer: D Answer'Explanation s /1 Justification: Choice Basis orJustification Correct: D Thelisted valves(MO-2-10-039BandMO-2-10-34B) are required to beopen tocoolthetorususing the Unit 2 RHR "B" ("B" loop RHR Pumpor"D"RHRPump). Thesevalves are powered from Load Center E424,Answer D iscorrect.
Distractors: A Load Center E334powers the similar valves forUnit 3"A"RHRfor torus cooling. Answer A isincorrect.
torus cooling. Answer B isincorrect.
C Load Center E324 powersthe similar valves forUnit 2"A"RHRfor torus cooling. Answer C isincorrect.
Page:65of214 16March 2020
i 2020NRCROExamrev0 Test ID:330066 Question 28Einfo < ... . ..
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficul : 0.00 S stemID: 2129547 User-Defined ID:
Cross Reference Number:
Topic' 2b. State thepower supplies tosystem For components: AC comonents less than thet e 4kV,state NumField 1:
NumField 2:
Text Field:
Page: 66of214 16March 2020
ji 2020NRCROExamrev0 Test ID: 330066 Comments: None
- None fff Eff None Pschometrics Level of RO Knowled e Memory 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT OtherPrevio X ed Bank Bank us2 NRC Exams Reference(s): COL10:1.A-2B Learning PLOT 5010, -
2b Ob^ective:
K/ASystem:219000 RHR/LPCI: Importance:
Torus/Suppression Pool RO / SRO Coolin Mode 2.5/2.9 K/A K2.01 Knowledge power ofelectrical Statement: supplies tothe followin :Valves REQUIRED None MATERIALS:
Notes and None Comments:
Page: 67of214 16March2020
= = = =,
n 2020NRCROExamrev0 Test ID: 330066 MRIAWiWabi jdli#WWS'W Adifif?fjAV//fkfE$350%W$kWW%atta&fdW YAAfAA53598 Unit 3is at100% power.
a a constant input of contaminated watertotheUnit 3 RBFloor Drain Sumpexists a ofBOTHUnit3 afailure RB Floor Drainsumppumps occurs Which oneofthe following describes theeffect oncontamination levels inthe Unit 3 SumpPumpRoom andwhy?
Contamination levels intheUnit 3 Sump Pump Roomwill:
A. rise because the sumpwill overflow to the roomfloor.
B. not beaffected because the sump is sealed andexcess input willbackup tothesource.
C. not beaffected because the sumpwilloverflow directlytotheFloor Drain CollectorTank before the top oftheFloor Drain Sumpisreached.
D. notbeaffected because the sumpwill overflow directly to the RBEquipment Drain Sumpbefore thetopofthe Floor Drain Sumpisreached.
Answer: D Answer Explanation 3 Justification: Choice Basis orJustification Correct: D Thedesign"of theFloor Drain sumps andEquiprnent Drain sumps isthatthey will drain totheother the if sumppumps stop working.
Theoverflow willthen bepumped outbythe functioning pumps.
Distractors: A Plausibleif candidate misinterprets the design ofthe sumps and doesnotrecognize thecross connecting pipes B Plausibleif candidate misinterprets the structural design ofthe sumps asthey are ona lower elevation andareopen to atmosphere they would first overflow totheother sumpandthen overflow onto the floor. .. ...
C Plausibleasthesumppumps forRBFloor Drain pumptothe Floor DrainCollector tank. However theFloor Drain Collector tank isat a higher elevation than the sumppumps andthey would not overflow into the tank.
Page: 68of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Question 29Info' Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 1 Difficult: 1.00 S stemID: 993171 User-Defined ID: ILT-5020-2D-001 Cross Reference Number: 268000 K3.04 To ic: ILT-5020-2d-001 Loss ofFloor Drain Sums NumField 1:
NumField 2:
Text Field:
Comments: PMT'TTffjffj$ji None F([GffTGT"ETifffjff,ff$f($ None EMfff*[($Mff(ff[ffffffjj$ None EM5[ff(f[(fif((dffj$$$ None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(13)
Source Documentation Source: New ModifiILT Other Previo ed Bank Bank us2 X NRC Exams Reference(s): PLOT5020; M-369 Learning PLOT-5020-6d Ob'ective:
K/ASystem: 268000Radwaste -
Importance:
RO/SRO 2.7/ 2.8 K/A K3.04Knowledge oftheeffectthat a loss Statement:ormalfunction of theRADWASTE willhaveonfollowing:
Drain sums REQUIRED None MATERIALS:
Notes and None Comments:
Page: 69of214 16March2020
2020NRCROExamrevo Test ID:330066 A33%$DWAb@%5dE@fSW2$jfdi$$A2$WA0@$$$ddANYMEW IAWthe assumptions inthePBAPS UFSAR accidentanalysis for acontrol roddrop accident, which ofthe following isdesigned to maximize the amount oftime it takes for acontrol rod todrop outofthe core?
A. TheCRD blade velocity limiter.
B. TheCRDblade cooling water line.
C. TheCRDmechanism collet fingers.
D. TheCRDmechanismcoupling spud.
Answer: A Answer Explanation CCA2 Ann .
E, n M s Justification:
Choice Basis or Justification Correct: A IAWthePBAPSUFSARaccident analysis ofa control rod drop accident (section "The velocity atwhich 14.6.2): the control rod fallsout ofthecore isassumed tobe5ft/sec. Thecontrol rod velocity limiter(3),
anengineered safeguard,limits the rod drop velocity toless than this value." Thusthe CRDblade velocitylimiter is designed tolimit the speed atwhich thecontrolroddrops outof the core,orin other words, itmaximizes theamount oftime it take todrop out ofthe core. Answer Aiscorrect.
Distractors: B TheCRDcooling waterline comes inatthebottom oftheblade and flows upward. Iftheflowandpressure werehigh enough, itmayimpact thespeed atwhich the control rod falls. Raising CRDcooling water flow/pressure isonemethod toinsert control rods duringa hydraulic ATWS.CRDcooling water isnotlisted intheaccident analysis. Answer B isincorrect for butplausible thereasons listed.
C This answer isplausible since the CRDmechanism collet fingers are designed topreventa latched control rod from withdrawing withouta withdraw signal butisnotmentioned intheaccident analysis for a rod drop accident. Answer C isincorrect.
D This answer isplausible since theCRDcoupling spudisdesigned to ensure that theCRDblade iscoupled totheCRDmechanism. The control rod drop accidentassumes that the CRDblade hasbecome uncoupled from theCRDmechanism anddoesimpact thespeed drop inthe accident for analysis a control roddrop accident. Answer D is incorrect.
Page:70of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Question 30Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toCom lete: 0 Difficult: 0.00 S stemID: 2130447 User-Defined ID:
Cross Reference Number:
Topic:
. 3a. Describe CRDMandRPIS the Systems feature(s) design and/or interlock s andfor initial candid NumField 1:
NumField 2:
Text Field:
Page: 71of214 16March 2020
2020 NRCROExamrev0 Test ID: 330066 Comments: KffT(ff/Aff(((GR((ff(f((f(f((tWW'f'#?s None None None F/ None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): USAR14.6.2 Learning PLOT 5003, -
3a Ob'ective:
K/ASystem:201003 Control Rodand Importance:
Drive Mechanism RO / SRO 2.9/3.0 K/A K4.01 Knowledge ofCONTROL ROD AND Statement:DRIVEMECHANISM design feature(s) and/or interlocks whichprovidefor the following: Limiting control rod speedinthe event ofa roddro REQUIRED None MATERIALS:
Notes and None Comments:
Page: 72of214 16March 2020
2020NRCROExamrev0 Test ID: 330066
?@fithddif$rkhkWRMM@WWWMl4WW&&iY@%WFW" 2isoperating at 65% power Unit
= Alarm (201 E-4)"4B Heater High Level" issealed-in duetoatube leak inthe'4B' Feedwater Heater
= 4BFeedwater Heater Drain and DumpValves arefullopen
= 4B Feedwater Heaterlevel isrisingslowly Oneminute later:
= 4B Feedwater Heater level risesto the High-High condition Which oneofthe followingvalve positionsis correct?
W M (AO-8120B) (AO-2315B1 A. OPEN CLOSED B. OPEN OPEN C. CLOSED CLOSED D. CLOSED OPEN Answer: D Answer Explanation
<<Justification:Choice BasisorJustification Correct: D Inaccordance with ARC201E-4 AO-8120B goclosed and will AO-2315B wW goopen duetohigh level Distractors: A Plausible asthese arethenormal valve positions whileoperating andthecandidate maymisinterprettheneedfor automatic operation ofthesevalves.
B Plausible asthis ispartially correct,however theAO-8120B valve willgoclosed andthecandidate maymisinterprettheautomatic operation ofthis valveata highlevel inthe Feedwater heater.
C Plausible asthis ispartially correct,however theAO-2315B valve willopenandthe candidatemaymisinterprettheautomatic o eration ofthis valveata hihlevel inthe Feedwater heater.
Page: 73of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Question/3t info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 3 Difficult: 2.00 . . . .
S stemID: 993324 User-Defined ID: ILT-5001E-4D-001 Cross Reference Number: 256000 K5.03 Topic: ILT-5001E-001 2isoperating Unit at65%Reactor powerwith the "4B Heater HihLevel" alarm NumField 1:
NumField 2:
Text Field:
Page: 74of214 2020 16March
j; 2020NRCROExamrev0 Test ID:
330066 Comments:
FM)%jW($ None WC?%[ff(ffffffffj/7))JEf@ None
&[Lif$ff(((f'MMTA None 3Wfffj None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(7)
Source Documentation Source: New ModifiILT Other Previo ed Bank Bank us2 X NRC Exams Reference(s PLOT5001E.04D; M-304, ARC-201 E-4 Learning PLOT-5001E-3d Ob'ective:
K/ASystem: 256000 -
Importance:
Reactor RO/ SRO Condensate 2.6/ 2.7 S stem K/A K5.03Knowledge ofthe operational Statement: implications ofthe following concepts asthey apply toREACTOR CONDENSATE SYSTEM
- Heat exchan erlevel o eration REQUIREDNone MATERIAL S:
Notes and This question meets theK/AastheFeedwater Comments:Heater System istheHeatExchanger associated withtheReactor Condensate System. Thequestion tests knowledge of operational implications bytesting the candidates knowledge ofautomatic valve operations that respond toHeat Exchanger levelo eration.
Page: 75of214 16March 2020
n ne : :m e a a eE.
2020NRCROExamrev0 Test ID: 330066 DF2ffid d2@2#7///2#///7/#2/>1WMYADWW/////22WffdPhDA Unit 2isoperating at 100% power whenRPSBusB de-energizes duetoa sustained electrical fault.
Which oneofthe following identifies a radiation monitor that isaffected bythis electrical loss andhowthe radiation monitor fails?
A. 'B' Main Stack Radiation Monitor; fails low B. 'B' Main Stack Radiation Monitor; fails as-is C. 'B' and'D' Main SteamLine Radiation Monitors; fail low D. 'B' and'D' Main Steam LineRadiation Monitors; fail as-is Answer: C AnswetExplami$6nf Choice Basis orJustification Correct: C RPSBusB supplies power to 'B' and 'D' Main Steam Line radiation monitors. Onloss ofpower, these radiation monitors fail low.
arepowerecfifom 200Wand- 20034 Distracters: A Main Stack radiation monitors (UPS powered panels), not the RPSBuses. Plausible because these aresimilar radiation monitors andtheir power supply is also 120 VAC.
B Main Stack radiation monitors arepowered from20Y050 and20Y034 (UPS powered panels), notthe RPSBuses. Plausible because these aresimilar radiation monitors andtheir power supply is also 120 VAC.Theradiation monitors fail low, not as-is. Plausible because someother radiation monitors fail as-is onloss ofcertain power D TheMain (ex.
suppliesRBCCW SteamLine onloss radiation of30Y033).
monitors faillow, notas-is. Plausible because someother radiation monitors failas-is onloss ofcertain power (ex.
suppliesRBCCWonloss of30Y033).
Page: 76of214 16March 2020
, e- ,e
, ,/ :
2020NRCROExamrevo TestID:330066 32linfioE Question Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: O Difficult: 0.00 S stemID: 1659126 User-Defined ID:
Cross Reference Number: 272000 K6.01 To ic: RPS Bus B loss affectonMSLradiation monitors NumField 1:
NumField 2: A NRC Text Field:
Comments:
Ps chometrics of Level Diffic Time RO Knowledgeulty Allowance minutes Memory 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT OtherPrevio ed Bank Bank us2 NRC X Exams (21148 X 15 Reference(s) M-1-S-26, ARC218D-3, PLOT-5063 Learning PLOT-5063-7a Ob'ective:
K/ASystem:272000 Radiation Importance; Monitoring RO/SRO 3.0/3.2 K/A K6.01Knowledge ofthe effect thata lossor Statement: malfunction ofthe followingwill have onthe RADIATION MONITORING SYSTEM:
Reactor rotection s stem REQUIREDNone MATERIALS Notes and None Comments:
77of214 Page: 16March 2020
j 2020NRCROExamrev0 TestID:330066 hird2$F13df2fffdfffffdfdfthdthWdfthddFvWddf?dh!itEU!!!
Unit2isat100% power a arebeing Adjustments made toFIC-8636 "OxygenFlow Control" perchemistry request
= 230C-2"Offgas Oxygen Conc High/Low" onthe Recombiner Panelalarms Which oneofthefollowing describes theoxygen concentration that wouldcause this alarm andthe automatic actionassociated with the alarm?
Theoxygen concentration is--(1)--
AND OnUnit 2atrip hasoccurred onthe--(2)
A. 1)30%
2)ntire E Hydrogen Water Chemistry System B. 1)30%
- 2) Oxygen side ofHydrogen WaterChemistry system ONLY C. 1)45%
2)Entite Hydrogen Water Chemistry System D. 1)45%
2)Oxygen side ofHydrogen WaterChemistry system DNLY Answer: C 78of214 Page: 16March2020
2020 NRCROExamrev0 Test ID: 330066
<<Choice Basis orJustification Correct: C Inaccordance with ARC230C-2, the highalarm for setpoint oxygen concentration is45%.Theautomatic actionsassociated with thisalarm isafull trip oftheHydrogen Water Chemistry sys.tem Distractors: A Plausiblebecause whensetting upOxygen flow theconcentration isset bewteen 16and25%,soaconcentration of30%is higher thanthis andthe candidate maymisinterpret this ashigh enough to bring inthealarm.
Second part iscorrect B Plausible because when setting upOxygen flow theconcentration isset bewteen 16and25%,soaconcentration of30%ishigher than this and the candidate maymisinterpret this ashigh enough to bring inthe alarm.
Plausible asthe alarm isassociatedwith a high Oxygen concentration and the candidate maymisinterpret the systemonly isolating theOxygen side tobring theconcentration backwithin padis D correct Plausible asthe alarm isassociated with a high Oxygen concentration andthe candidate may misinterpret the systemonly isolating the Oxygen side tobring the concentration back within band.
Page: 79of214 16March 2020
E 2020 NRCROExamrevo Test ID:330066 Question 33I!nfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stem ID: 2130838 User-Defined ID: ILT-5015-4D Cross Reference Number: 271000 A1.14 To ic: ILT-5015-4d Ox en asconcentration NumField 1:
NumField 2:
Text Field:
Page: 80of214 16March 2020
2020 NRCROExamrevo Test ID: 330066 Comments: N////////////A8$($(((f"PM((d lf2$f 1?
Level of
/ Ps chometrics RO Knowled e Memo 10CRF55.41 b7 Source Documentation Source: X New Exam Previous NRCExam item Modified Bank Other ExamBank ILT Exam Bank Reference( ARC230C-2, PLOT-5015, SO15.1.A-2, SO s: 8.1.A-2 LearningPLOT-5015-4d Ob'ective:
K/A 271000Offgas Importance:
System: System RO / SRO 2.7/3.0 K/A A1.14Ability topredict and/or monitor Statement: changes in parameters associated withoperatingthe OFFGAS SYSTEM controlsincluding: Oxygen asconcentration REQUIREDNone MATERIAL S:
Notes and This question meets theK/Aasoxygen isfed Comments:into theOffgas systemjustbefore theoffgas recombiner pre-heaterandissampled before andafter theguard bed.Adjustments of oxygen flowwould affectrecombination of hydrogen andoxygen. Thisquestion teststhe candidates knowledge ofthe consequences of anout ofbandOx en asconcentration.
Page: 81of214 16March 2020
i; 2020NRCROExamrev0 Test ID:330066 Ag'f"@p"Fggjgig?ffW$W$QggffgfffffQvM$"fggfgfffjjrfffligigggygggggglipilgffff#ffig):
Unit2isatpower during astartup with the following parameters:
= Reactor power is 80%
= Core flow is74%(of rated)
Duringacontrol rod withdrawal, the Recirculation Loop"A"flow input into ARPM1fails downscale.
Which ofthe following states theimpact onthe plant, andwhat action canbetaken tocontinue the startup?
APRMScram:
(Note: 0.60WD + 65.9%; ARPM Rodblock: 0.60WD + 56.5%)
PlantIIripact Actioft A. a A recirculation flow mismatchBypass APRM1IAWSO62.7.A-2, alarm generated byRodBlock"Receipt ofRodBlocks" Monitor "A".
B. a A recirculation flow mismatchBypass RBM "A" IAWSO alarm generated byRodBlock62.7.A-2, "Receipt of RodBlocks" Monitor "A".
C. a A recirculation flow mismatchBypass APRM1IAW SO 62.7.A-2, alarm generated byRodBlock"Receipt ofRodBlocks" Monitor "B".
D.
- A recirculation flow mismatchBypass RBM"B" IAWSO alarm generated byRodBlock 62.7.A-2, "Receipt ofRodBlocks" Monitor "B".
Answer: A Page: 82of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: A Eachof4 APRMsreceives aseparate flow input from each recirculation loop (driveflows from r ecirculation loops A andB.).
APRM1inputs recirculation flow intoRodBlock Monitor "A" (with APRM3asa backup), andAPRM2 inputs recirculation flow into Rod Block Monitor "B"(with backup from APRM4). WhenoneRBM senses a >10%in recirculation flows,that RBMgenerates a recirculation flow mismatch alarm. At1/2 (37%) ofthe actual core flow (74%), the APRMpower setpoint fora rodblock is0.60x37 + 56.5% =
22.2 + 56.5% = 78.7% power. Since actual power of80%isabove the rodblock setpoint, APRM1will generate acontrol rodblock. Thus, there is a recirculation flow mismatch alarm from RBM"A", anda control rod block from APRM1.Theprocedure allows action to bypass APRM 1 When this isperformed, RBM"A" nowreceives its recirculation flow input from APRM3 instead ofAPRM1,andthe recirc flow alarmis cleared becauseit sees normal recircflow indications from anAPRM withnormal recirculation flow inputs .
Bypassing APRM1also bypasses the control rod block from APRM1, andthe startup maycontinue.
Distractors: B This answer isplausible since the firstpart ofthe answer iscorrect.
TheRBMinits current state, with 0 recirculation flow from 1 recirculation loop, canstillperform its function toprovide control rod blocks from over-power. There isa bypass joystick which doesallow for bypass ofa RMB,but iwtould not be pypassed under the conditions inthe question stem.
C This answer isplausible since there will bearecirc flowmismatch alarm andcontrol rodblock. If the student misinterprets the RBMlogic such that APRM1 recirculation flow goes toRBMB, then this choice could becorrect.
D This answer isplausible since there will bea recirc flow mismatch alarm andcontrol rodblock. thestudent if misinterprets the RBM logic such that APRM1recirculation flow goes toRBMB,then this choice could becorrect.
Page: 83of214 16March 2020
4:A:3 An ,,
i:
2020NRCROExamrevo Test ID: 330066 QuestionN1nfo ...... . .. . . . ..
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: 0.00 S stemID: 2129646 User-Defined ID:
Cross Reference Number:
Topic:
. 7f. Determine theeffect that ormalfunction a loss ofthe followin willhave onthePowerRaneNe NumField 1:
NumField 2:
Text Field:
Page: 84of214 16March 2020
,;x 2020NRCROExamrev0 Test ID: 330066 Comments: hsaM"'"/"'"#"V?$?:?Rigji None None p None ii"""
Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(5)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): ARC211A-3, ARC211 B-2, SO62.7.A-2, ARC211A-4, GP-5-2Exhibit 1,TS3.3.1.1 Learning PLOT 50607f -
Ob'ective:
K/ASystem:215002 RodBlock Monitor importance:
RO/SRO 3.3/3.3 K/A A2.02 Statement:following Ability (a) to predict the ontheRODBLOCKMONITOR impacts of the SYSTEM ;and(b) based onthose predictions, useprocedures tocorrect, control, ormitigate the consequences of those abnormal conditions oroperations:
Loss orreduction inrecirculation system flow flow com arator :BWR-3,4,5 REQUIRED None MATERIALS:
Notesand None Comments:
Page: 85of214 16March 2020
2020 NRCROExamrev0 Test ID: 330066 tW?Al?WiffMidd?WWiffff7ffkibMM"''MP2/Ah VWAF)f$88fifW Unit 2 isat100% reactor power with recirculation flow at100%, whenthefollowing occurs:
ALLNarrowRange levelinputs toDFWCfail
= Reactor WaterNarrow Range Level indicators (analog) are functional still Whichofthe following statesthe plant impact iafctual reactor water level were torise uncontrollably with NOoperatoraction?
A. There beNOautomatic will feedwater pumptrip from a high RPVwater level.
B. Thefeedwater pumps will automatically trip atthe DFWCS high water level setpoint, but ACTUAL water level (indicated on analog narrow range) will behigher.
C. Thefeedwater pumps will automatically trip atthe DFWCS high water level setpoint, but ACTUAL water level (indicated on analog narrow range) will belower.
D. Thefeedwater pumps will automatically trip at theDFWCS high water level setpoint, and ACTUAL water level (indicated on analog narrow range) will be thes ame.
Answer: B Answer Explanationd A .
Justification:Choice Basis orJustification Correct: B TheDigital Feedwater Control System (DFWCS) uses the 3 narrow range RPVwater level instruments (primary) todetermine feedwater flow into theRPV.If all3water levelinputs arefoundto be failed by DFWCS,it willdisregard the narrow range inputs andswap over and usethe2wide range instrument inputs. But, athigh reactor power andhigh recirculation flow, asinthe question stem, the widerange water level instruments indicate several inches lower than actual on narrow range (approximately 10inches). Thus, whenthe control system swaps fromnarrow range towiderange, itwillseeRPVabout 10inches lower than actual onnarrow range. WhenRPVwater level does govery high, the feedwater pumps will tripatthe highwater level setpoint, but RPVACTUAL onnarrow range levelwill behigher than this (by about 10inches).
Distractors: A This answer isplausible if thecandidate misinterprets howthe DFWCS works with failed RPVwater level inputs.Seeabove.
C This answer isplausible if the candidate misinterprets howthe DFWCS works with failed RPVwater level inputs.Seeabove.
D This answer isplausible if the candidate misinterprets howthe DFWCS works with failed RPVwater level inputs.Seeabove.
Page: 86of214 16March 2020
s 2020NRCROExamrev0 Test ID: 330066 Question!35 Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficul : 0.00 S stemID: 2130452 User-Defined ID:
Cross Reference Number:
Topic:
. 6a. Determine the effect that a loss ofthe ormalfunction Feedwater/Feedwater S stemwill Control h NumField 1:
NumField 2:
Text Field:
Page: 87of214 16March 2020
4tix 2020NRCROExamrev0 Test ID: 330066 Comments: P/////////MM None
'f None
F None None Pschometrics Level of RO Knowled e High 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): PLOT 5006, PLOT-5002b, SO6D.7.E-2 Learning PLOT 5006, -
PLOT-5002b Ob'ective:
K/ASystem:216000 Nuclear Boiler Importance:
Instrumentation RO/ SRO 3.4/3.4 K/A A3.01 Abilitytomonitor automaticoperations Statement: ofthe NUCLEAR BOlLER Instrumentation including:
Relationship between meter/recorder readin sandactual arametervalues REQ UIRED None MATERIALS:
Notes and None Comments:
Page: 88of214 16March 2020
2020NRCROExamrev0 Test ID: 330066
$E3@1AWf5%A$if$$d$$f&bW@i$iD@$$
Thefollowing conditions exist onUnit 2:
October 1stat08:00:Unit 2 isshutdown for a refueling outage
- Prior totheshutdown, Fuel Pool heat load isnegligible.
= 320Fuel Assemblies from the core are offloaded intothefuel pool.
a FuelPool Gates arere-installed At07:30onOctober 11,the following annunciator alarmed:
= FPHXINLET HDR/RHR HXHPSW OUTLET HITEMP(ARC 224D-5) a Thecontrolroom operator reports Fuel Pool Heat Exchanger nlet I Header (point temperature 28) on TRS-2-10-131 atPanel 20C004C is127F.
October 11at08:00:
= FuelPoolHeat Exchanger Inlet Header temperature is130F.
A completeloss ofcooling totheFuel Pool isconfirmed
= FuelPoolcooling CANNDI berestored Whichoneofthe following isthe earliestap.proximate amount of time it take will for theFuelPoolwater torise temperature to200F?
A. 3.5 hours B. 5.5 hours C. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D. 10hours Answer: C Answer ExplanationA AA Correct: C PerAO19.3-2 for a 320bundle offload at10daysafter shutdown, starting with a fuel pool water temperatureof130degreesF,it will takeapproximately 8hours.
Distractors: A Thisanswer represents thelength oftimeWreach 200degreesF,if starting atafuel pool watertemperature of130degreesF for afull coreoff-load instead ofjust 320bundles (different off-loaded, graph butcorrect water temperature).
B Thisanswer represents thelength oftimetoreach200degreesF,if graph ata fuel starting but pool incorrect water water temperature temperature).
of150degreesF (same D Thisanswer represents thelength oftimetoreach200degreesF,if graph ata fuel starting but pool incorrect water water temperature temperature).
of110degreesF (same Page: 89of214 16March 2020
- : :::::x x = ::=
SRSW0; 2020NRCROExamrev0 Test ID: 330066 Questiond36:info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 5 Difficult: 2.00 S stem ID: 2131052 User-Defined ID:
Cross Reference Number: 233000 A4.05 To ic: ILT-5019-3a-002 Loss ofFPC time-to200F NumField 1:
NumField 2:
Text Field:
Comments:
Wiff7ffAj Yes:AO19.3-2 fWffffffW None ffj(ffiWfMfff"f'"T['$ffhffffjf) None Vjffffff(f((([(fffl2ffff(((f$fifffffffj None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(7)
Source Documentation Source: New ModifiILT Other Previo ed Bank Bank us2 X NRC 20838 Exams 11 Reference(s): AO 19.3-2 Learning PLOT 5019, -
6a Ob'ective:
K/ASystem:233000 Fuel PoolCooling Importance:
andClean-up RO/SRO 2.7/3.1 K/A A4.05 Ability tomanually operate and/or Statement:monitor inthe control room: Pool tem erature REQUIRED Copy ofAO19.3-2 MATERIALS:
Notes and None Comments:
Page: 90of214 16March2020
^t)tL BRM%WMM&%MiBVMEffff/fJAliMERRMFMMW#RF/WERAFAi The following conditions exist onUnit 3:
- Unit was shutdown for refueling outageonJanuary 5that03:00.
= 320 Fuel Assemblies from the corehave been offloaded(fuelplaced inFuel Pool).
= Prior to the shutdown, Fuel Pool heat loadwasnegligible.
= At03:00 on January 23rd ofthesameyear, theFuelPooltemperature is100F.
Ifacomplete loss of cooling tothe Fuel Pool occurs onJanuary 23rdat03:00, determine then the ap.proximate amount of time it will takefortheFuel Poolwatertemperature to150degrees torise (assuming cooling tothe Fuel Pool isNOIrestored).
A. 3hours B 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> C. 11hours D. 15hours Answer: B A$18dDkpi8Mil88WE33Ab1 '
d T 12 . b Correct: B PerAO19.3-3 a 320bundle offload at18days for after S/D(initial 100deg.) ..
Distractors: A Represents the time to150degrees from a completecore offload.
Plausibleif candidate misinterpretsa 320 bundle offload asa complete core offload andchooses the wrong chart time~to150 C Representsthe degrees'froma 320 bund'le'offload (initial 70degrees). if Plausiblecandidate assumeshighest curveonchart isthe100degree curve.
D Represents the toboil time from a 320bundle core offload. Plausible ifcandidate onthe plots time toboil chart andnotthe 150 degree chart PB-OPS-EXAM-lLT-2015 1of2 Page: 12March2020 Current View
4t488804%/h A E%
Question T e: MultileChoice Status: Active Alwasselect ontest? No Authorized forractice? No Points: 1.00 Time toCom lete: 5 Difficult : 2.00 S stemID: 2083811 User-Defined ID: B NRC2019 Cross Reference
~-
Number: , .
233000 A4.05 NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of DifficultyTime RO Knowledge Allowance minutes High 10CRF55.41(b)(5 Source Documentation Source: New Examitem X Previous NRC Exam(2019)
Modified Bank X Other ExamBank (LORT 2034940)
X ILT Exam Bank (2115421)
Reference(s AO19.3-3 Learning PLOT-5019-3a Ob'ective:
K/ASystem: 233000Fuel -
Pool Cooling Importance:
andClean-up RO /SRO 2.7/ 3.1 K/A A4.05Ability tomanually operate and/or Statement: monitor inthecontrol room: Pool temerature REQUIREDcandidates mustbegiven acopyofAO MATERIAL 19.3-3 S:
Notes and None Comments:
Associated objective(s):
6a. Determine theeffect that ormalfunction a loss oftheFuel PoolCooling andCleanup System will have onthe following: FuelPool Temperature PB-OPS-EXAM-lLT-2015 Page: 2 of2 12March 2020 Current View
4 2020NRCROExamrev0 Test ID:330066
$k" ??ljMkWMWhiAfWf/AfMA$&D46%bMdWAdjM8i$$4 Whichoneofthe following instrument scram setpoints listedbelow willrequire entry into orapplication ofa 2 Tech Unit Spec, while in Mode1?
A. Drywellpressure of1.9 psig.
B. RPVwater level of2 inches.
C. Scram DischargeVolume of48gallons.
D. Main condenser vacuum of 20inches Hg.
Answer: D AnswerExplanation A C ..
Justification: Choice Basis or Justification Correct: D Themain condenser receives steam discharged from the final stages ofthe lowpressure turbines. TS Table 3.3.1.1-1 lists scram setpoints forvarious parameters. Ifa scram setpoint exceeded the setpoint,the instrument would beinoperable and a TS entry orapplication be will required.Thescram setpoint for maincondenser vacuum is2 21.5 inches Hg.Thus a setpoint of20inchesHg for condenser vacuum is less thanallowed byTS.
Distractors: A TSTable 3.3.1.1-1listsscram setpoints for various parameters. If a
scram setpointexceeded the setpoint, theinstrument would be inoperable andaTSentry orapplication will berequired. Thescram setpointfor Drywell pressure is5 2psig. Thus a setpoint of 1.9psig fordrywell pressure meets the TS.This answer isplausible since Drywell pressure ismonitored anddoes provide ascram signal on high Drywell pressure. All setpoints,including thecorrect answer, are close tothe actualsetpoint.
B TSTable 3.3.1.1-1listsscram setpoints for various parameters. If a
scram setpointexceeded thesetpoint, theinstrument would be inoperable andaTSentry orapplication will berequired. Thescram setpointfor RPVwater level is2 1 inch. Thusa setpoint of2 inches forRPVwater levelmeets theTS.This answer isplausible sinceRPV water level ismonitored anddoes provide a scram signal onlowRPV water level.Allsetpoints, includingthe correct answer, areclose tothe actual setpoint.
C TSTable 3.3.1.1-1listsscram setpoints for various parameters. If a
scram setpointexceeded the setpoint, theinstrument would be inoperable andaTSentry orapplication will berequired. Thescram setpointfor SDVwater level is5 50gallons. Thus a setpoint of48 gallons for SDVwater level meets the TS.This answer isplausible since SDVwater level ismonitored anddoesprovide ascram signal onhigh SDVwater level. Allsetpoints, including the correct answer, areclose toth Page:91of214 16March2020
i; 2020NRCROExamrev0 Test 330066 ID:
Question"37 Info 1 Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2129706 User-Defined ID:
Cross Reference Number:
Topic: 13.Given a set ofconditions related Protection totheReactor S stem RPS reco s stemarame nize NumField 1:
NumField 2:
Text Field:
92of214 Page. 16March 2020
2020NRCROExamrev0 Test ID:330066 Comments: 'WMWR"* #'"##*"7'F"UTE None F/ None None None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)()
Source Documentation Source: New Modifi ILT OtherPrevio X ed Bank Bank us2 NRC Exams Reference(s): TS3.3.1 Learning PLOT 5060F, -
13 Ob'ective:
K/ASystem:239001 Main andReheat importance:
Steam System RO/SRO 3.9/4.6 K/A G2.42 Abilitytorecognize system Statement: parameters that are entry-level conditionsfor Technical S ecifications.
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 93of214 16March 2020
li; ;
2020NRCROExamrev0 Test ID:330066
'//
/ // : ',
, . / ' ' '
/ . .
oneofthe following would Which beaneffect ofa loss ofthe Unit 2 PPC(Plant Process Computer) onthe oftheUnit2 RWM (Rod function Worth Minimizer)?
A. RWMloses theability tomonitor controlrod positions.
B. RWMlosesthe ability toenforce theloaded control sequence.
rod C. RWMloses theability toprovide both control rodpermissives andblocks.
D. RWMloses theability to display andinterface with theHMI(Human Machine Interface).
Answer: D Answer Ekplanations Justification: Choice Basis orJustification Correct: D PPCprovides thehuman machine interface for theRWM.Without it the operator cannolonger provide input into theRWMandthe RWMwill nolonger display properly Distractors: A Plausible asthe operator canmonitor controlrod positions through PPC,however theRWMreceives its input directly from Rod Position Indication(RPIS) andwillstill receive positions ifPPCis B lasible asthe control rodsequence'is loaded through PPC, however theRWMstores this sequence locally anddoes notneed PPCtoaccess. PPCwould beneeded inorder to loadadifferent sequence.
C Plausible asthe operator receives their information of RWM supplied permissives androdblocks through the PPC interface, however even whenPPCisdowntheRWMwill provide the still permissives androdblocks directly totheReactor ManualControl S stemRMCS Page:94of214 16March 2020
2020NRCROExamrevo Test ID:330066 Question 38info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: 0.00 S stem ID: 2130840 User-Defined ID: ILT-5062A-7D Cross Reference Number: 201006 K6.04 To ic: ILT-5062A-7d lossofPPConRWM NumField 1:
NumField 2:
Text Field:
Page: 95of214 16March 2020
i 2020 NRCROExamrev0 Test ID: 330066 Comments: a!"W:*?l WPA&W:T"f((ff((f((((f(j((($ None iF' None None Pschometrics Level of RO Knowled e Memory 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT OtherPrevio X ed Bank Bank us2 NRC Exams Reference(s): PLOT-5062A Learning PLOT-5062A-7d Ob'ective:
K/ASystem:201006Rod Importance:
Worth RO/SRO Minimizer 2.7 /2.8 System RWM K/A K 6.04Knowledge oftheeffect thata loss Statement:ormalfunction ofthe following willhaveon the RODWORTHMINIMlzER SYSTEM (RWM) (PLANT SPECIFIC) :Process com uter REQUIRED None MATERIALS:
Notes and None Comments:
Page: 96of214 16March2020
2020NRCROExamrevo Test ID: 330066 A@'@$khikifff$fkk)Riii1Arfff$Y$$$ij$WM$(Affaf&$58W MWVfff4Ah(?41%
Unit 2isat100% power
= T-104,"Radioactivity Release Control" isentered onvalid radiation monitor alarms Inaccordance with T-104 bases, which ofthe following correctly the completesstatements:
Theradiation monitor alarms used to enter T-104 "Radioactivity Control" Release are.(1).-
above release normal rates AND Therelease rate upon firstentering T-104 "Radioactivity Release Control" pose
--(2)- animmediate threat tothe public.
A. 1)slightly 2)doesnot B. 1)significantly 2)doesnot C. 1)slightly 2)does D. 1)significantly 2)does Answer: B Page: 97of214 16March 2020
2020NRCROExamrevo Test ID: 330066 Choice Basis orJustification Correct: B T-Wis"ente"recfon'Main Stack orVent Stack Rad abovethe"Hi Hi alarm setpoint. Inaccordance with T-104 bases "Main andVent Stack radiation high-high alarm levels aresignificantly abovethe normal release rates andareindicative ofdegrading plant conditions.
However, these levels arelow enough that the release does pose not animmediate threat tothe public andsubsequent actions could prevent exceedingODCM limits.!' ..
Distracters: A Plausible asthere are someradiation alarms that are just slightly above normal rad levels toindicate there isa problem. Theones used to enter T-104 arehowever theHi-Hi rad alarms andwould alarm at a much higher than normal release rate.
Second part iscorrect C Plausible asthere aresomeradiation alarms that are just slightly above normal rad levels toindicate there isaproblem. Theones used toenter T-104 are however theHi-Hi rad alarms andwould alarm ata muchhigher than normalrelease rate.
Plausible asT-104 isdesigned tolimit theradioactivity release into thepublic andfurther inthe procedure are actions related torad levels that areanimmediatethreat tothepublic. Butnotwhenfirst entering T-104 D First part iscorrect Plausible asT-104 isdesigned tolimit the radioactivity release into thepublic andfurther intheprocedureare actions related torad levels that areanimmediate threat tothepublic. But whenfirst not enterin T-104 Page: 98of214 16March 2020
2020NRCROExamrevo Test ID:330066 Question 39Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2131802 User-Defined ID:
Cross Reference Number: 295038 K1.02 To ic: T-104 ent and eneral ublic rotection NumField 1:
NumField 2:
Text Field:
Comments: Psychometrics Levelof Difficulty Time Allowance RO Knowledge (minutes)
MEMORY 10CFR55.41(b)
(10)
Source Documentation Source: X NewExamitem Previous NRCExam Modified Bank Other Exam Bank ILT ExamBank Reference(s): T-104 andbases Learning PLOT-PBIG-2104 5 Objective:
K/A System: 295038 HighOff-site Releaseimportance; Rate RO 4.2 K/A K1.02Knowledge oftheoperationalimplications Statement: ofthefollowing concepts asthey apply toHigh Off-site ReleaseRate: ofthegeneral Protection public REQUIREDNONE MATERIALS:
Notes and Comments:
Page: 99of214 16March2020
= == -
2020NRCROExamrev0 Test ID: 330066
$4A%iffikidff$bN/fM$f$fifWdifAMT$$)AWMW%%ifffffAfffW$ikk&h$A Unit 2 isoperating in Mode 4:
= A sustained lossof shutdown cooling occurs.
= Thebest estimate to start a recirculation pumpis2hours from now.
ON-125,"Loss ofShutdown Cooling", directsraising RPVlevel toabove +50inches.
IAWON-125, which oneofthe following states the reason for this action?
A. Provides additional NPSH for placing a Recirculation pumpinservice.
B. Ensures temperatures andthermal stresses intheRPVhead flange areminimized.
C. Promotes natural circulation andhelps prevent stagnation ofcoolant inthe core.
D. Establishes a longer "time toboil" whilealigning alternate decay heat removal systems.
Answer: C Answer Explanation Correct: C PerON-125 Bases, raising level toabove the separators (> +50 inches) promotes natural circulation, which willpreventstagnation (thermal stratification) ofreactor coolant.
.---.This Distractors: A isnot thebases per ON-125, butisplausible since adding inventory will enhance recirc pumpNPSH. Inaddition, +50inches is more than isrequired for recirculation pumpNPSH since normal RPV water level isless than 50inches.
B This answer isplausible since ifwater level'was""rafsedto the flange area, it could mitigate the temperature atthe flange. Butthe RPV flange iswayabove the water level of50inches.
inventory will lengthen thetime toboil.
(
I Page: 100of214 16March 2020
2020 NRCROExamrev0 Test ID:330066 Question40info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 3 Difficult: 1.00 S stem ID: 994770 User-Defined ID: ILT-1550-28C-001 Cross Reference Number: 295021 AK1.02 Topic:
. ILT-1550-28C-001 2isoperating Unit inMODE4whena sustained loss ofshutdowncoolin occcurs.
NumField 1:
NumField 2:
Text Field: NRC-09-1 Comments:
EIfTFK#r4if5f77571Rii220 None FWf1[CT7WfAff3f(gi None MM[ffffj((ff"C*~T[(fffEff None FMiM(ff6 None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(10)
Source Documentation Source: New ModifiILT Other Previo ed Bank Bank us2 X NRC Exams Reference(s): OT-125,OT-125 Bases Learning PLOT PBIG-1550, 128c Ob'ective:
K/ASystem:295021 LossofShutdownImportance:
Cooling RO/SRO 3.6/3.7 K/A AK1.04 Knowledge oftheoperational Statement:implications ofthe following concepts asthey toLOSS apply OFSHUTDOWN COOLING: Natural circulation REQUIRED None MATERIALS:
Notes and None Comments:
Page: 101of214 16March2020
si 2020 NRCROExamrev0 Test ID:330066 A:WR45##%&dW/?%#dffWF2Wdh$$MAJi$@@W$314)Ad2##MB Thefollowinginitial conditions exist:
= Unit2is operating at fullpower a Unit3isshutdowndue toa small steam leak resulting in2.3psig intheDrywell A trip oftheSU-25 breaker (452-02) occurs, resulting ina partial loss ofelectrical power. Thirtyseconds the later, PROreviews the 4KVbus and annunciator status with the following results:
= E-13, E-22, E-33, E-42 arepowered bytheirnormal Emergency Auxiliary Bus
= E-12, E-32, andE-43 transferred toan alternate Emergencysupply
= E-23isdeenergized with annunciatorE23 BUS UNDERVOLTAGE (002 D-4) lit a AllfourDiesel Generators arerunning normally Which oneofthe following describes thecause ofthe undervoltage condition ontheE23bus?
A. ONLYthe E-223 breaker failedtoclose on theauto transfer.
B. ONLYthe E-323 breaker failedtoclose onthe auto transfer.
C. BOTHthe E-223 breaker andthen theE-23 Diesel Generator output breaker failed to close onthe auto transfer.
D. BOTHtheE-323 breaker andthen theE-23 Diesel Generator output breaker failed to close onthe auto transfer.
Answer: D Answer Explanation . . . . . .. . . . . . .
Choice Basis orJustification Correct: D TheSU-25 powers the 2 SUEtransformer, which isthe normal supply ofpower toE-23 through E-223. With power tothe2 SUE lost transformer, thealternate supply breaker (E-323) should have closed in0.25 seconds. With thediesel available, thediesel outputbreaker should haveclosed after 0.5seconds if thebus wasstiIIdeenergized.
Distracters: A Plausible ifthe candidate misinterprets electrical distribution system.
The E-223 isthenormal power supply tothis busandit haslost power duetothetrip ofthe SU-25 breaker.
B Plausible astheanswer ispartly correct. Although E-323should have closed, theDiesel Generator output breaker (E-23)hasalso failedtoclose.
C Plausible asthe answer ispartly correct astheDiesel Generator Output breaker (E-23) hasfailed toclose, however E-223isthe normal power supply tothe busandlost power duetothe ofthe trip SU-25 breaker. Itdid not fail toclose. Thealternate startupsource breaker E-323 failedtoclose.
Page: 102of214 16March 2020
E 2020NRCROExamrevo Test ID: 330066 Questiott 41Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult : 2.00 . .
S stem ID: 995495 User-Defined ID: B CERT Cross Reference Number: 295003 AK1.05 . .
To ic: ILT5054-7b-006 A & BCERT NumField 1:
NumField 2: A CERT Text Field:
Comments:
3fffffffjT",'F'f'"W//ffff None N,"E""'"Q":$E Jffjjffffff(ffffff None ffMC"'ffff'fffffffff)((fffffffffd None FMW($ff None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(8)
Source Documentation Source: New ModifiILT Other Previo ed Bank Bank us2 X NRC Exams Reference(s): COL54.1.A, Learning PLOT 5054-7b -
Ob'ective:
K/ASystem:295003 Partial or Importance:
Complete Loss ofA.C. RO/SRO Power 2.6/2.7 K/A AK1.05 Knowledge ofthe o perational Statement:implications ofthe following concepts asthey apply toPARTIAL OR COMPLETE LOSSOFA.C. POWER:
Failsafe comonent desi n REQUIRED None MATERIALS:
Notes and None Comments:
Page: 103of214 16March2020
2020NRCROExamrev0 Test ID: 330066 RhPW$b'*%A&?#W/ffW f%Wf)ffffWM5%5kkhki d dkMWt&#Aidll$rfA00 IAWthePlantSafety Analysis oftheUFSAR (Chapter 14), during refuel activities, which ofthe following prevents inadvertent criticality duetoa control rod withdrawal error bythe panel operator?
A. TheReactor Mode switch islocked intheREFUEL position.
B. Theenforcement oftheBoundaryzone bytheRefuel Bridge PLC.
C. Anoperable WRNM isin thecore quadrant where fuel isbeing moved.
D. TheRWMis verified operable, with keylock it's switch inNORMAL.
Answer: A AnswerExplanation x . . . ...
Justification: Choice Basis or Justification Answer A Thenuclear characteristics of the core assure thatthereactor is subcriticaleven initsmost reactive condition withthemostreactive controlrod fullywithdrawn during refueling. Whenthe modeswitch is inREFUEL, only onecontrol rod can be withdrawn atatime. Selection ofa second rod initiatesarodblock(in RMCS), thereby preventing the withdrawal ofmorethan onerod atatime. Thus, if 1control rodis withdrawn, RMCS will notallow the withdraw of a second control rod.
Distractors: B This answer isplausible since thesystem canprevent movement ofa loaded hoist over the core. TheRefuel Bridge PLC does enforce the Boundary zone which isdesigned toprevent movingthe bridge/hoist intothewalls ofthefuel pool,transfer canal, andtheRPV. Itwillnot prevent theinserting ofa fuel bundle into anuncontrolledcell inthe core.
C This answer isplausible since Operable WRNMs inthe core quadrant istoensure the ofthe ability control room tomonitor counts asfuel is beingwithdrawn orinserted into thecore. WRNMcanenforce a rod blockonhigh counts.
D This answer isplausible because theRodWorth Minimizer backs-up controlroom operators, whofollow procedural controlstolimit the consequences ofaControl RodDrop Accident (CRDA), during the timeswhenthe fuelismostsusceptible todamageinduced bya ControlRodDrop Accident (CRDA) -
during lowpowers atstartups andshutdowns. TheRWMisnotrequired tobeoperable inMode5 Refuelin Page: 104of214 16March 2020
2020NRCROExamrev0
- i Test ID: 330066 Question 42htfo' . .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stem ID: 2129709 User-Defined ID:
Cross Reference Number: 295023 AK2.04 Topic: Predict theoperational orcause-effect implications relationships resultin from the o eration oft NumField 1:
NumField 2:
Text Field:
Page: 105of214 16March 2020
A ;
2020NRCROExamrev0 Test ID:330066 Comments: 425% ;L ()p fd(W((((f$ffff(dWff((($
None V None F// None Pschometrics Level of RO Knowled e Memory 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us NRC Exam Reference(s): UFSAR 14.5.3.3 Learning PLOT 5018 -
Ob'ective:
K/ASystem:295023 Refueling Importance:
Accidents RO /SRO 3.2/3.4 K/A Ak2.04 Knowledge oftheinterrelations Statement: between REFUELING ACCIDENTS andthe following:RMCS/Rod control andinformation s stem REQUIRED None MATERIALS:
Notes and None Comments:
Page: 106of214 16March 2020
a 2020NRCROExamrev0 TestID: 330066 Akard"GBd&LirW/rWWfif(fff!fbMfd$%AbykffT/?WShiitW$5 Unit2 isat100% power whenthe main trips.
generator 1minute the later, following parameters arenoted:
= ReactorPressure is914 psig
= 15controlrods doNOTindicate full-in
= Itisverified that theMAXIMUM SUBCRITICAL BANKED WITHDRAWAL POSITION criteria hasbeen met Which ofthefollowing identifies 1)Thestate ofthe reactor AND 2)Theoperator action tobeperformed based onthe conditions A. 1) Thereactor isNOTshutdown under ALLconditions
- 2) Maintain current pressure reactor until all control rods are full in B. 1)Thereactor isNOTshutdown under ALLconditions
- 2) Maintain current reactor AND pressure inject boron C. 1)Thereactor isshutdown underALLconditions 2)Commence a normal cooldown D. 1) Thereactor isshutdown underALLconditions 2)Maintain current reactor pressureuntil all control rods full are in Answer: C 107of214 Page: 16March 2020
'/:
- j; ' ' '
TSDSWt 2020NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: C With'a"rn'ai'n gen'erator tripatrated power, theu'nit w'ill scram.
Following the scram, indications showthat 15control rods donot indicate full-in, but thecriteria for theMAXIMUM SUBCRITICAL BANKED WITHDRAWAL POSITION (MSBWP) hasbeen met.
IAW T-101 BASIS: "Note #24defines whenanATWSis terminated.
- 1) By definition, all rods inserted toorbeyond the Maximum Subcritical Banked Withdrawal Position (MSBWP) willmaintain the reactor shutdown under all conditions without boron. or, 2)Anysingle rod withdrawn past 00and all other rods full-in meets the design basis shutdownmargin that assures thereactor willremain shutdown with single strongest control rod full-out andall other rods full-in.or, 3)The Reactor Engineer may also determine whenthe ATWSis terminated because theREmaintains thenecessaryqualifications andhas access toresourcesnecessary tomakethis determination."
Since MSBWP hasbeenmet, regardless ofhowmanycontrol rods do notindicate full-in, thereactor will remain shutdown under all conditions, andany ATWScondition may beterminatedandthus no ATWSevent actions arerequired.With thereactorshutdown under all conditions, a cooldown maycommence. Finally, although notall control rods fullyinserted ona scram, the reactor isdetermined tobe shutdown.
Distractors: A This answer isplausible since itstates that15 control rods donot indicate full-in, although their exact positions are not given. If the candidate misinterprets the definition ofMSBWP,they may believe the reactor isnot shutdown under allconditions. With the reactor not shutdown the candidate would bestopped inT-101 and maintain reactor pressure until the ATWSisnolonger present orother criteria B h nswer indicate full-in, isplausitile although since their i@iven exact that 15control positions are rods notgiven.
donot Ifthe candidate misinterprets thedefinition ofMSBWP,they maybelieve the reactor state isnot shutdown under all conditions. With thereactor not shutdown thecandidate would bestopped inT-101 andmaintain reactor pressure until the ATWSisnolonger present anddepending onpower level would beinjecting boron.
D Plausible since thereactor isshutdown under allconditions because the Maximum Subcritical Banked Withdrawal Position (MSBWP) has been met.However the candidate might misinterpret the definition of anATWS,inthat anATWSis terminated whenall but onecontrol rod isinserted toposition 00andtherefore thereactor should not be deressurized.
Page:108of214 16March 2020
2020 NRCROExamrevo Test ID:330066 Question43Info' ..... .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: 0.00 S stemID: 2129827 User-Defined ID:
Cross Reference Number:
To ic: 4.State TRIP terms anddefinitions.
NumField 1:
NumField 2:
Text Field:
Page:109of214 16March 2020
2020 NRCROExamrev0 Test ID: 330066 Comments: FS/////A532llll%[((f(f((""'f""iifliiji$?"'"/"c None 2125MN22MfMW/fAiilV52225 None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)7()
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): T-101, T-101 Bases, TRIP CURVES, TABLES& LIMITS APPENDIX I Learning PLOT PBIG-2101, -
4 Ob'ective:
K/ASystem:295006 Scram Importance:
RO/ SRO 4.2/4.3 K/A AK2.06 Knowledge oftheinterrelations Statement:between SCRAMandthe followin :Reactor Power REQ UIRED None MATERIALS:
Notes and None Comments:
Page: 110of214 16March 2020
j 2020NRCROExamrevo Test ID: 330066 Unit 2 isat100% power
= Toruswater levelbegins tolower
= All attemptstomitigate the rate ofwater level loss have failed
= Currenttoruswater level is 12.4 feet, andlowering IAWT-102, "PrimaryContainment Control", before Torus water level lowers another 2feet, theOperator bedirected will toopen all ADSvalves.
IAWT-102 Bases, which ofthefollowing states thereason forthis action?
This willhelptoprevent ..
A. exceeding the SRVTail Pipe Limit.
B. over-pressurizing theTorus airspace if a LOCA occursin theDrywell.
C. exceeding the Torus design negative pressure ifTorus Spraysareinitiated.
D. over-pressurizing theTorus airspace if theSRVtail pipe vacuum open.
fail breakers Answer: B Page: 111of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: B Thequestion states that Torus water levelislowering, andall attempts tomitigate the water level losshave failed. TheDrywell downcomers become uncovered inthe Torus water space at10.5 feet. Thus, any steaminthe Drywell goes downthedowncomers andinto the Torus air space,and this will pressurize the Torus air space. With Torus water level above 10.5 feet, then the steam going downthe downcomer into the Torus water space willbecondensed with no direct pressurization ofthe Torus air space from steam. T-102 requires an emergency blowdown whenTorus water level cannot be maintained above 10.5 feet.Inthe question with Torus water levelat 12.4 feet,then water level lowering anadditional 2 feet, Torus water level is10.4feet and emergency blowdown isrequired before this value. Blowdown is accomplished inT-112, bymanual opening ofall ADSsafety relief valves.
T-102 provides the following: "Torus level must bemaintained above 10.5 feet,the elevation ofthe downcomer vent openings, toensure that steam discharged fromthe drywell into the Torus following a primary system break will beadequately condensed." It also says:
"10.5 feet isthe Torus elevation ofthe LOCA downcomer vent openings. Whenthedowncomer vent openings are not adequately submerged, steam from the RPVinto Primary Containment maynot beadequately condensed intheTorus before Torus pressurereaches unacceptable values. Emergency RPVdepressurization isrequired by this step atorbefore Torus leveldrops to10.5feet." Thus, prior to reaching 10.4 feet water levelinthe Torus, all ADS valves mustbe manually opened toprevent Torus air space over-pressurization ifa LOCAwere tooccur.
Distractors: A This answer isplausible since theSRVtail pipe limit isrelated to Torus water level, but isonly aconcern onhigh Torus water level.
E This answer"is plausible since a primary contahment negative pressure could occur through both evaporative andconvective cooling, andthrough inappropriate operation ofDrywell andTorus Sprays.
There areactions inthe T-102 procedure onwhentostart andstop theDrywell/Torus sprays toprevent a negative pressure inthe Primary Containment. But, this isnot a reason for thequestion, IAWT-102 Bases.
D This answer isplausible since ifanSRVtail pipe vacuum breaker should failopen, then pressurizing the Torus air space could occurthe next time the SRVwasopened.
Page: 112of214 16March2020
2020NRCROExamrev0 i7e Test ID: 330066 C
Questions441l!nfowne x .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 2 Difficult: 2.00 . ..
S stemID: 2130463 User-Defined ID: ILT-2102-7A-028 Cross Reference Number: 295030EK2.07 To ic: ILT-2102-7A-028 Bases forblowdown at10.5 NumField 1: COMP2 -6467 NumField 2: N/A Text Field: A Comments:
kWEfffffj None
@@ffj f['[G'T"'Tiffffjf[(fffff) None frM[rM$(((d None (Wj@f(d None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(7)
Source Documentation Source: New ModifiILT Other Previo ed Bank Bank us2 X NRC (99411 Exams 6)
Reference(s): T-102, T-102 Bases Learning PLOT PBIG-2102, -
7a Ob'ective:
K/ASystem:295030 LowSuppression importance:
Pool Water Level RO/SRO 3.5/3.8 K/A EK2.07 Knowledge oftheinterrelations Statement: between LOW SUPPRESSION POOLWATERLEVELand the following: Downcomer/ horizontal vent submer ence REQUIRED None MATERIALS:
Notes and None Comments:
Page: 113of214 16March2020
Ort)/Ar MMM7/J1t//75/////////f///////////M72AW//////ff82MPA8FJ Unit 2wasoperating at100%power whena pipe leak upstreamofMO-13A, "2ARHRPumpSuction" has resulted inanunisolable leak inthe Torus. Torus levelis13feetandlowering.
Inaccordance withT-102, anEmergency blowdown mustbeperformed at10.5 ft.
inorder to:
A. minimize thedrivingforce ofthe primary systembreach.
B. depressurize the reactor duetothe downcomer ventsbeing uncovered.
C. depressurize thereactor duetotheSRVtailpipes being uncovered.
D. prevent the Heat Capacity Temperature curve Limit from being exceeded.
Answer: B 4MSS$f8Nddill$tbC2$3idddff@Md QuestionT e: Multi leChoice Status: Active Alwasselect ontest? No Authorizedforractice? No Points: 1.00 TimetoCom lete: 2 Difficult m
2.00 S stemID: 994116 User-Defined ID: ILT2102-7A-022 CrossReference Number: 295030EK2.07 mamm=emmer To ic: ILT-2102-7A-022 Basesfor blowdown at10.5 NumField 1: COMP26467 NumField 2: N/A TextField: A Comments: Importance RO/SRO: 3.5/3.8
Reference:
T-102 Bases A.Incorrect:
B.Correct:
C.incorrect: SRVtailpipesuncover at7feet D.Incorrect:
Associatedobjective(s):
7a.State the purpose andapplicability foreach ofthefollowing support procedures from directed T-102, Primary Containment Control including system geography anssystem implications/operationaleffects:[G2.4.34, G2.4.35, G2.4.16)
T-200, Containment Primary Venting PB-OPS-EXAM-lLT-2015 Page:1of1 12March 2020 CurrentView
A 2020NRCROExamrev0 TestID: 330066 ABf*...x' gWhyA$$$1M*#fdfiffamoiPWWWSfdfAfrtfifif fff!WWESSRshristrairrisid:M:tati)jaitsillitime Unit 2 isat100% power whenthe following occurs:
event a Condensate Pump 2A suction valve (MO-2093A) fails closed a Theplant stabilizes Whichofthe following describes the expected change inflow indication,andthereason for thischange?
(Assume NOoperator actions)
A. COREPLATEFLOW (Red Pen)indication lowered duetoanASDRunback to30%
speed.
B. JETPUMPTOTALFLOW(Black Pen)indicationlowered duetoanASDRunback to 45%speed.
C. COREPLATEFLOW(Red Pen)indication lowered APRMindication duetoa lowering to30%power.
D. JETPUMPTOTALFLOW(Black Pen) indication lowered APRM duetoa lowering indication to45%power.
Answer: B Page:114of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: B Thestemstates thatthe suction valve toCondensate Pump2A goes closed. Whenthe suction valve comes offtheopen seat,the condensate pump trip.
will Whenreactor power is> 85%power and anycondensatepumpbreaker the trips, ASDrecirculation pump control system will runback bothrecirculation pumps to45%speed.
This will result ina lowering oftotalcore flow anda lowering ofcore delta-p.
Distractors: A The ASD recirculation pumpcontrol system also hasa runback to 30% speed from severalsignals, but not thesamesignal asthe 45%speed runback. Thusa 30%recirculation pumpspeed hasnot occurred. This answer is plausible ifthe candidate misinterprets ASDlogic.
.C Itisindeed true that when reactor recirculation pumps runbackto 45%speed, there is a reduction in reactor power andCore PlateDp, but power does notgo as low as30%,asindicated inthedistractor.
Power lowers towithinthe capacity of2 condensate pumps. Reactor power stabilizes atapprox. 65% power. This answer isplausibleif the candidate misinterpretsthe plant response toa condensate pumptrip.
D Itisindeed true that whenreactor recirculation pumps runbackto 45%speed, there isa reduction inreactor power andJetPumpflow, butpower does notgoaslowas45%,as indicated inthe distractor.
Power lowers towithin the capacity of2 condensate pumps. Reactor power stabilizes atapprox. 65%power. This answer is if plausible the candidate misinterprets theplant responseto a condensate um tri Page: 115of214 16March2020
2020 NRCROExamrev0 TestID:330066 Question ~45 Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2130486 User-Defined ID:
Cross Reference Number: .. . . .
Topic:
. 3r.Describe the Reactor /Recirculation Recirculation Flow Control S stems desi nfeature s and/or NumField 1:
NumField 2:
Text Field:
116of214 Page: 16March 2020
2020NRCROExamrev0 Test ID:330066 Comments: None liaiiEWW/4iiBRWff(((("t(tdAW(iRRiffr((fdi F None P/ None
' None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): ARC203E-2 Learning PLOT 5002, -
3r Ob'ective:
K/ASystem:295001 Partial or Importance:
Complete Loss ofForced RO/ SRO Core Flow Circulation 2.9/3.0 K/A AK3.06 Knowledge ofthereasons forthe Statement: following responses asthey apply toPARTIAL ORCOMPLETE LOSSOFFORCED COREFLOWCIRCULATION: Core flow indication REQUIRED None MATERIALS:
Notes and None Comments:
Page:117of214 16March 2020
- ~
1
. n
.. n n =
2020NRCROExamrevo Test ID:330066 A$#%d2dBfdf13fddPff#fdfEM$f%d%fddf212f///d3D%d Unit 2isat100% power
= A fire isreportedby the Hydrogen Seal Oil System
= OilfromtheMain Seal Oil pump isspraying outandfeeding thefire Inaccordancewith ON-114 "Actual FireReported in thePower Block, DieselGenerator Building, Emergency Pump,Inner Screen,or Emergency Cooling Tower Structures"which ofthefollowing states therequired andwhy?
action ACTION REASON A. Shutdown Hydrogen Seal Oil ONLY Mitigate damage bystopping oil supply to the fire B. Shutdown Hydrogen Seal Oil ONLY Remove power electrical tocomponents for Fire Brigade members safety C. Isolate ANDVent the Main Generator Mitigate damage bystoppingoil supply to THEN thefire Shutdown Hydrogen Seal Oil D. Isolate ANDVent the Main Generator Remove electrical power to components THEN for Brigade Fire memberssafety Shutdown Hydrogen Seal Oil Answer: C Page:
118of214 16March2020
2020NRCROExamrev0 Test ID: 330066
<<<<Choice Basis orJustification Correct: C Inaccordance with ON-114, for a fireaffecting theHydrogen Seal Oil System attachment 3would beperformed. This vents themain generator andthen secures theHydrogen Seal oil system. Thisis doneinaccordance with ON-114 bases torapidly shutdown the oil pumps tomitigatedamahping the oil sup@tothe fire.
Distractors: A Plausible asthe fireisbeing fedbytheHydrogen Seal Oilsystem andrapidly shutting downoil pumps ispart ofthe bases for ON-114, however duetothesystem affected, Hydrogen mustbe vented first before shutting downthe seal oil system, otherwise Hydrogen mixedwith air could cause aworse explosion.
Reason given is correct B Plausible as thefire isbeing fed bytheHydrogen Seal Oilsystem andrapidlyshutting downoil pumps ispart ofthe bases for ON-114, however due to the system affected, Hydrogen mustbe vented first before shutting down theseal oil system, otherwise Hydrogen mixed with air could cause aworse explosion.
Plausible asremoving power from components would be performed toprotect the Fire Brigade members, however ON-114 andtheSOprocedures only shutdown the system anddonot shutdown thepower suppliesto the system. This would be researched andrelayed separately to have breakers opened tothe related equipment for protection.
D First part iscorrect Plausible asremoving power from components wouldbe performed toprotect the Fire Brigade members, however ON-114 andthe SOprocedures only shutdown the system anddonot shutdown the power supplies tothe system. This would be researched andrelayed separately tohave breakers opened tothe related equipment for protection.
Page: 119of214 16March 2020
/i 2020 NRCROExamrev0 Test ID: 330066 Questioni46 Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: 0.00 S stemID: 2131809 User-Defined ID:
Cross Reference Number: 600000 AK3.04 Topic: 19d Specific toON-114, Actual Reported Fire inthe Power Block, Diesel Generator Buildin NumField 1:
NumField 2:
Text Field:
Page: 120of214 16March 2020
- i; 2020 NRCROExamrev0 Test ID
- 330066 Comments: F#23N45l$f?RTT"'f""1lVARlllRf((R$l
/
Level of Diffi Time Ps chometrics RO Knowle cult Allowa dge y nce (minut es Memo 10CRF55.41 b 10 Source Documentation Source:X NewExam Previous NRCExam item Modified Bank Other ExamBank ILTExamBank Referen ON-114 andbases ces :
Learnin PLOT-1550 9
Objecti ve:
K/A 600000PlantImportance:
SystemFire onSite RO/SRO 2.8 /3.4 K/A AK3.04Knowledge ofthereasons forthe Statemfollowing responsesasthey toPlant apply on Fire ent: Site: Actions contained intheabnormal procedure for thelant onsite fire REQUI None RED MATER IALS:
Notes none and Comme nts:
Page: 121of214 16March 2020
m ,
2020NRCROExamrevo Test ID: 330066 WJagablfthfff&Afffffff@ji MEf7/Wffil$(ffhfffhVAMWffidWfffkiWWAAffBj$jifaf$jgitBf$
Thecrewhasentered andisexecutingSE-16, "Grid Emergency".
a Thestation emergency electrical system isinadegraded condition Inaccordance with SE-16 "Grid Emergency", atshift managements discretion, theStationBlackout (SBO)
LoadBreak Switch '00S079' would be.-(1)-.
this Performing onthe '00S079' Load Break Switchwill R.)-.
A. 1) OPENED orverifiedOPEN
- 2) improve the ofthe 361-00 line reliability B. 1) OPENED orverified OPEN 2)ready the191-00 linefordedicated use C. 1) CLOSED orverified CLOSED 2)improve thereliability ofthe 361-00 line D. 1) CLOSED orverified CLOSED
- 2) ready the 191-00 linefordedicated use Answer: B Answer ExplanationT . . . 1
<<Choice Basis orJustification Correct: B inaccordance with step 3.7 ofSE-16, atshift managements discretion,ifthe station emergency system is ina electrical degraded condition, 00S079 would beopened. This is to take initial action toready the191-00 line fordedicateduse.
Distractors: A Firstpart iscorrect Second partisplausible asthe load switch breaker 00S079 is connected tothe 361-00 line andthe maymisinterpret candidate theconnection asadding moreinstability toanalready unstable C F stpaWausible asnormaVthe 00S079 lives opened andthe""
candidate maymisinterpret the step toclosethe00S079 to improve thereliability ofthe 361-00 lineormisinterpretgrid lineup.
D Firstpart isplausible asnormally the 00S079 lives opened andthe candidate maymisinterpret the step toclosethe00S079 or misinterpret grid lineup.
Secondart iscorrect Page:122of214 16March2020
2020 NRCROExamrev0 Test ID: 330066 Questiort47 info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 2 Difficult : 1.00 S stem ID: 2130848 User-Defined ID: ILT-1555-3-031 Cross Reference Number: 262001K3.05 Topic: ILT-1555-031 SE-16 for Purpose SBOLoad opening Break Switch 00S079 NumField 1:
NumField 2:
Text Field:
Page: 123of214 16March 2020
ii 2020NRCROExamrevo Test ID:
330066 Comments: .5Mf51W "WT"L::~:W '"""fR
/
Pschometrics Levelof Diffi Time RO Knowle cult Allowa dge y nce (minut es Memo 10CRF55.41b 10 Source Documentation Source:X NewExam Previous NRCExam item Modified Bank Other ExamBank ILTExamBank Referen SE-16 andbases, E-5343 ces :
Learnin PLOT-1555 9
Objecti ve:
K/A 700000- Importance:
SystemGenerator RO/SRO Voltage and 3.6 /3.9 ElectricGrid Disturbances K/A AK3.02Knowledge ofthereasons for the Statemfollowing responsesasthey apply to ent: GENERATOR VOLTAGE ANDELECTRIC GRID DISTURBANCES: Actions contained inabnormal operating procedure for voltage andgrid disturbances REQUI None RED MATER IALS:
Notes none and Comme nts:
Page:124of214 16March 2020
r; 2020NRCROExamrev0 Test ID:330066 J$jA 2;aigfW Ag$ffffffiRus3Mi$@N1Afirk 4f45RA2MWfffFS#$2r/2iirtheih Unit 2hasexperienced a loss ofDrywell cooling anda steam leak intheDrywell with thefollowing:
Drywell spray hasbeen initiated duetohigh Drywell per temperature Containment "Primary T-102, Control".
= Drywell temperature is230F andloweringslowly a Drywell pressure is6 psig and lowering slowly oneofthefollowing Which identifiesthecorrect parameters for spray whenDrywell tobe isrequired inaccordance secured with T-102?
Secure Drywell spray before:
A. Drywell Pressure drops below 2 psig OR Torus Level reaches 18ft B. Drywell Pressure drops below -2psig OR Torus Level reaches 18ft C. Drywell Pressure drops below 2psig OR Torus Level reaches 21ft D. Drywell Pressure drops below 2 psig OR Torus Level reaches 21ft Answer: A Page:125of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Choice Basis orJustification Correct: A T-102 requires securing Drywell sprays beforeDrywell Pressure drops below 2 psig OrTorus 18ft reaches level Distracters: B Plausible as-2psig isalso containedinT-102 inthePC/Plegtovent primary containment ic if tannot bemaintainedabove-2psigandthe candidate maymisapply the numbers.
Second part iscorrect C First part is correct Plausible as21ft ismentioned inboth thePC/Pleg andDW/Tleg of T-102as a limitation onstarting theTorusSprays candidate andthe maymisapply thisinformationn . .
D Plausible as-2 psig isalso containedinT-102 inthePC/Plegtovent primary containment ifictannot bemaintainedabove-2psigandthe candidate maymisapply thenumbers.
Plausible as21ft ismentioned in the both PC/P legandDW/Tleg of T-102 asa limitation on starting theTorusSprays andthe candidate ma misa I this information.
Page: 126of214 16March 2020
"i 2020NRCROExamrev0 Test ID:330066 Questiott 48Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult : 0.00 S stemID: 2131856 User-Defined ID:
Cross Reference Number: 295028 EA1.04 To ic: PLOT-2102 -
Whentoterminate s ras-2 NumField 1:
NumField 2:
Text Field:
Comments: Psychometrics Level of Difficulty Time Allowance RO Knowledge (minutes)
Memory 10CFR55.41(b)
(10)
Source Documentation Source: NewExamitem Previous NRC Exam X Modified Bank(2114933)
Other Exam Bank ILT ExamBank Reference(s): T-102 Learning PLOT-PBlG-2102 5 Objective:
K/A System: 295028 -
High Drywell importance; Temperature RO 3.9 K/A EA1.04 -
Ability tooperate and/or monitor the Statement:following asthey apply toHigh Drywell Temperature: Drywell pressure REQUIREDNONE MATERIALS:
Notes and Thequestion meets theK/Abypresenting a Comments: situation where Drywell sprays have been initiated duetohigh Drywell temperature and requiring knowledge ofwhenDrywell sprays areterminated based onD ellressure.
Page:127of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Wi4R$!@+ AibffA$'""QMU '"'4$jf)%D$$$$f$$RMWffffj$@f$M@$W$15%$Rfifff$$$AS Unit 2 isat28%power ona plant startup whenthe annunciator following alarms:
= MAINTURBINE EMERGENCY TRIP Whichofthe actions have following NOTbeen states the correct performed yet.)
plant responses30seconds (assume later? GP-4operator 1.BothsetsofScram Group lightsare de-energized onpanels 20C015 and20C017 2.Theback-upscram valves solenoids are de-energized.
3.All scram dischargevolume vent anddrain valves indicate red lights on.
SCRAM 4.Annunciator DISCH VOLUME NOT DRAINED (ARC islit 210B-2)
MODESWITCH 5.Annunciator SHUTDOWNSCRAM BYPASS islit (ARC211A-2)
A. 1and4 ONLY B. 2and3 ONLY C. 1,4,and5 D. 1,2,and4 Answer: A Page:
128of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: A ThePlant wasat28%power whenannunciator MAINTURBINE EMERGENCY TRIPcamein. This alarm indicates a turbine triphas occurred. IAWthe ARC(205 B-4), ifreactor power isgreater than 26.3%, then anRPSactuated reactor scram also occurs. Since reactor power is28%,then the turbine tripwill result ina reactor scram. Whenascram occurs, the control room Scram Group lights(2 sets of 4,which arenormally energized) deenergize. Choice 1s correct.
Ona scram, thenormally energized scram pilot valves areenergized andwill de-energize tofacilitate ascram. But the normally de-energizedbackup scram solenoids willenergize toisolate andvent the scram air header, resulting in opening ofthe scram valves and scramming ofthecontrol rods.Since choice 2 states the backup scram solenoids arede-energized, andwill energize ona scram, Choice 2 isincorrect.
Ona scram signal, all scram discharge volumevent anddrain valves gofrom incorrect.
normally open toclosed(green lights Thus on). Choice 3is Ona scram signal, water from above the control rod drive pistongoes into the scram discharge volume (SDV) and the Annunciator SCRAM DISCH VOLUME NOTDRAINED willilluminate. And sincethe SDV vents/drains are closed, it cannot drain without operator action.Thus Choice 4iscorrect.
IAWGP-4, "Manual Reactor Scram", thesecond verifiable action is to place thereactor Modeswitch inSHUTDOWN. Whenthisis done, then annunciator MODESWITCH SHUTDOWN SCRAM BYPASS will comein. Since noGP-4actions have occurred yet, then Choice5 is incorrect.
Thus, Answer A iscorrect since both choices are correct for the resultant reactor scram from the turbine trip.
Distractors: B Answer B isplausible ifthe candidate misinterprets the turbine-scram interconnection andthe correct plant response toa reactor scram or misinterprets theannunciators provided inthe question stem.
C Answer C isplausible ifthecandidate misinterprets the turbine-scram interconnection andthecorrect plant response toa reactor scram or misinterprets the annunciators provided inthe question stem.
D Answer D isplausible ifthe candidate misinterprets the turbine-scram interconnection andthe correct plant response toa reactor scram or misinterprets theannunciators provided inthe question stem.
Page: 129of214 16March 2020
2020NRCROExamrev0 Test ID:330066 AAA Questiott 49;lrifo; Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficul : 0.00 S stemID: 2129852 User-Defined ID:
Cross Reference Number:
Topic:
. 30.Describe the Reactor System Protection (RPS)design feature s and/or s andfor interlock init NumField 1:
NumField 2:
Text Field:
Page: 130of214 16March 2020
i 2020NRCROExamrev0 Test ID: 330066 Comments: r/###a5#lF(ff"'iliAAAAANlligiAAAW((dil None P None
- None F/ None Pschometrics Level of RO Knowled e High 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT OtherPrevio X ed Bank Bank us2 NRC Exams Reference(s): ARC205B-4, ARC210 B-2, ARC211A-2, PLOT-5060F Learning PLOT 5060F, -
30 Ob'ective:
K/ASystem:295005 Main Turbine Importance:
Generator Trip RO/SRO 3.6/3.6 K/A AA1.02 Ability tooperate and/or monitorthe Statement:following as they apply toMAINTURBINE GENERATOR TRIP: RPS REQUIRED None MATERIALS:
Notes and None Comments:
Page: 131of214 16March2020
2020NRCROExamrev0 Test ID:330066 x5fdj@t$$lik(&'Wkfhf ai=Rfffhf)fAWABlifidhiff//fdhidif)W?ff/fA$%G91111172/k4)$2 Unit 2isat100%power whenthe annunciator following alarms:
a 2ADCPOWERPANEL LOVOLTAGE (ARC 209C-3)
Local investigation reveals that the 2ADCPower Panel hasafaultandshows 0volts.
Which ofthe followingstatesthecomponent which theControlRoomOperator isNOlonger ableto manually control from theControl Room?
A. CRDPump2B B. RHRPump2C C. Emergency Diesel E-1 D. CoreSprayPump2D Answer: C Answer Explanation . V m .. .... ...
Choice Justification: BasisorJustification Correct: C Theannunciator providesinthequestion stem describes a lowDC voltage condition onthe2A125VDCDistribution Panel (20D021).
Thispanelsupplies DCpower forbreakers for 4KV load breakers and powerforother things suchaslogic power. This means that there is noDCelectrical power needed toremotely close thebreaker to various loads. These loadsincludebreaker control andlogic power:
CRDPump2A,RHRPump2A,Core Spray Pump2A,RCIC, and emergency diesel generatorE-1.
Should4KVBusE12orE13lose power, emergency diesel E-1will NOTbeable tostartandload onto thebusfrom thecontrol roomand theBus(E12 orE13) belost.
will TheE-1cannot alsobemanually started/loaded from the control roomwith theDCloss. Thus Answer C iscorrect.
Distractors: A This answer isplausible sinceitalso requires DCpower foroperation, but DCsource that isnotthe2A Panel.
B This answer isplausible sinceitalso requires DCpower foroperation, but DCsource that isnotthe2APanel.
D This answer isplausible sinceitalso requires DCpower foroperation, but DCsource that isnotthe2APanel.
Page:132of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 50Irif6T A :
Question Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: 0.00 S stemID: 2129867 User-Defined ID:
Cross Reference Number:
2a.State the power supplies tosystem ForAC components:
Topic..
com onents less t han 4kV, s tatethe t e NumField 1:
NumField 2:
Text Field:
Page: 133of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Comments: TffA24:Y'"f**(((aiiitiiN%sp7ET"ff None V None
/ None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): ARC209C-3, SE-13 Leaming PLOT 5057 -
2a Ob'ective:
K/ASystem:295004 Partial or Importance: RO Complete Loss ofD.C. /SRO Power K/A AA1.03 Ability tooperateand/or monitor the Statement: following as they apply toPARTIAL ORCOMPLETE LOSSOFD.C. POWER: A.C. electrical distribution REQUIRED None MATERIALS:
Notes and None Comments:
Page:134of214 16March 2020
2020NRCROExamrev0 Test ID: 330066
$$3Ph;ishkhifiddkbiffkik AflMkbbVffff MihiiChi$259 Thecontrol roommust beevacuated.
Whichofthe followingstates a location where Unit 2Torus temperature mayberead?
A. TheRemote Shutdown Panel B. ADSAlternate Control Transfer Isolation Switch panel 2AC807 C. ADSAlternate Control Transfer Isolation Switch panel 2BC807 D. Alternate Control TransferIsolation Switchpanel 20C822 Answer: A A
Answer Explanation .
- .... .... x .
Justification: Choice Basis orJustification Correct: A Unit 2 torus temperature indicates on the Remote Shutdown Panel.
Distractors: B This answer isplausible since itmaybeneeded tobeaccessed during a control roomevacuation, but id toesnothave torus temperature indication.
C This answer isplausible since itmaybeneededto be accessed during acontrol room evacuation, but id toes nothave torus temperature indication.
.DThis answer isplausible since itmaybeneeded tobeaccessed during a control roomevacuation, but toesnothave id torus temperature indication.
Page: 135of214 16March2020
2020NRCROExamrev0 TestID: 330066 QuestionMil!nfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2129868 User-Defined ID:
Cross Reference Number:
Topic: 50.Describe therelationships between the Shutdown Remote Panel& Fire SafeShutdown/Alternative Sh NumField 1: N NumField 2:
Text Field:
Page:136of214 16March 2020
2020NRCROExamrevo TestID: 330066 Comments: f ff None P None jjj- None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(10)
Source Documentation Source: New Modifi ILT OtherPrevio X ed Bank Bank us2 NRC Exams Reference(s): SE-10, ST-O-013-750-2 Learning PLOT 5038X, -
50 Ob'ective:
K/ASystem:295016 Control Room Importance:
Abandonment RO/SRO 3.9/4.1 K/A AA2.04 Ability todetermineand/or interpret Statement: the following asthey toCONTROL apply ROOMABANDONMENT: Suppression pool tem erature REQUIRED None MATERIALS:
Notes and None Comments:
Page:137of214 16March 2020
pp :. ::= . .
2020NRCROExamrev0 Test ID: 330066
%ffA%#Wffs#fA22VAMW////AfA#W7/NaiRi2RR#%AREAM&asFAAi!#2thaMian Unit 2 isat100%power, withthe Backup Air Compressor tagged out ofservice,whenthe following occurs:
0758 "A"INSTRUMENT AIR HEADER LOPRESS and"B" INSTRUMENT AIRHEADER LOPRESS annunciators alarms 0800 TheReactor Operator reports INST AIRHDR"A"and"B" both indicate95psig, andlowering2 psig/minute.
0801 ON-119, "Loss ofInstrument Air"is entered 0802 TheReactor Operator dispatches Equipment Operators toinspect theinstrumentaircompressors andrelated components 0806 Instrument Air Compressor "A"trips 0808 INST AIRHDR"A" and"B"both indicate 79psig, and lowering 4 psig/minute.
0812 OneMSlVindicates splitindication 0813 Onecontrolrodbegins todrift 0814 Onecontrolrodscrams IAWON-119, whichofthe following represents theEARLIEST time that a GP-4"Manual Reactor Scram" should beperformed?
A. 0809 B. 0812 C. 0813 D. 0814 Answer: A Page: 138of214 16March 2020
A 2020 NRCROExamrevo Test ID: 330066 Justification: Choice Basis orJustification Correct: A IAWON-119, amanual scram isrequired under thefollowing conditions:
1)"IF both Instrument Air header pressures lowertoless thanorequal to75psig ORequipment tocontinued critical operation plant begins to malfunction duetolowair pressure, THENPERFORM GP-4, "Manual Reactor Scram"; and,
- 2) "lFat any timeduring the performance ofthis procedure anycontrol rodbegins to drift"in" duetolowering Scram air pilot header pressure ORMSlVsstart toclose,THENSCRAM ANDENTERT-100, "Scram" orT-101, "RPV Control" asappropriate ANDEXECUTE concurrently with this procedure."
Thus, at0808, air header pressure is given at79psig andlowering at 4 psig/minute. Attime 0809, airpressure indicates 75psig andisthe first event tomeetthe manual scram criteria inON-119. Answer A is correct.
Distractors: B This answer isplausible sincea closing MSlV isstated asascram point inON-119, but iitsnotthe first scram point met.
C This answer isplausible since a drifting control rod is statedasa scram point inON-119, but ii tsnotthe first scram point met.
D This answer isplausible sincelowair pressure canresult inopening of theHCUscram valves anda control rod scrams.
Page: 139of214 16March 2020
s ..
2020NRCROExamrevo Test ID:330066 Question Silnfor Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficul : 0.00 S stem ID: 2129869 User-Defined ID:
Cross Reference Number:
Topic:
. 22cSpecific toON-119, ofInstrument Loss Air Fora (IA):
sustained theim act loss ofIA,redict NumField 1:
NumField 2:
Text Field:
Page:140of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Comments: WJ/////////AMJV((f((((Gh$8(fffM"/None g None V None
""'f None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(10)
Source Documentation Source: New Modifi ILT OtherPrevio X ed Bank Bank us2 NRC Exams Reference(s):
Learning PLOT PBIG-1550, -
22c Ob'ective:
K/ASystem:295019 Partial or Importance:
Complete Loss of RO/ SRO Instrument Air 3.5/3.6 K/A AA2.01 Ability todetermineand/or interpret Statement: the following as they apply toPARTIAL ORCOMPLETE LOSSOFINSTRUMENT AIR: Instrument air s stem ressure REQUIRED None MATERIALS:
Notes and None Comments:
Page: 141of214 16March 2020
n nn, . n n y , .
2020NRCROExamrev0 Test ID: 330066
%#@W?WfM8WWWMlff&Wfd$WfifhDA 2isat100%power with Unit the conditions:
following
= A TBCCW isin service
= B TBCCW isinstandby
= TBCCWpressureis 71 psigandslowly lowering duetoa leak T=0the occurs:
following
= Fault on480VAC2G4-G-B occurs T=1minute
= TBCCWpressure is50psigslowlylowering
= Ann217C-5"TURBBLDGCOOLING WATER SUPPLY LOPRESS" Alarms Whichofthefollowing describes the system response without operator action?
A. ATBCCWremains running,B TBCCW auto starts B. A TBCCW remainsrunning,B TBCCW does not start C. A TBCCWtrips, BTBCCWauto starts D. ATBCCWtrips, B TBCCWdoes notstart Answer: B Page: 142of214 16March 2020
e m .
2020 NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: B TheA TBCCW pumpwill remain running astherearenoauto of trips the pumpexcept Pumpoverload. TheB TBCCWpumpwould notstart asits power supply hasa fault onit.
Distractors: A Firstpart iscorrect Second part isplausible asthe B TBCCW pumpwould auto with start pressure less then 70psig after a20second timedelay.However the B TBCCW pumpspower supply hasafault andthepumpwillnot start.
C Plausible asthe A TBCCWpumpishaving problemssupplying the correctpressure tocomponents and the candidate maymisapply this knowledge that the pumpwill automatically trip.
However theauto tripsofthe A TBCCW pumpis ona pumpoverload, andalthough the pumpmayeventually overload duetotheleak, itwill within nottrip one minute.
Second partisplausible as the B TBCCW pumpwould auto with start pressure less then 70psig after a20second timedelay.Howeverthe B TBCCWpumps power supplyhas afault andthepumpwillnotstart.
D Plausible astheA TBCCWpump ishaving problems supplying the correct pressure tocomponents and thecandidate maymisapply this knowledge that the pumpwill automatically However trip. theauto tripsofthe A TBCCW pumpisona pump overload, andalthough the pumpmayeventually overload duetothe leak, it within nottrip will one minute.
Secondart iscorrect Page: 143of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Question 53!lnfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2129870 User-Defined ID:
Cross,Reference Number:
Topic:
. 21a Specific toON-118, LossofTurbineBuildingClosed Coolin Water TBCCW S stem: Givenlant co NumField 1:
NumField 2:
Text Field:
Comments: P None "0"
"0" Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(10)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): M-316, sheet2 Learning PLOT PBIG-1550-21a Ob^ective:
K/ASystem:295018 Partial or Importance:
Complete Lossof RO/SRO Comonent Coolin Water3.2/3.5 K/A AA2.03 Causefor orcomplete partial loss Statement:
REQUIREDNone MATERIALS:
Notes and None Comments:
Page: 144of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 184k4#4EikWAff#f3V//tEAAMMAff#WWAssass#fA#4$AfellfidiPA$9 Unit 3 isat100%power
- aSafety Relief Valve fails fullopen andcannot beclosed
= Torus temperature is950F and rising Over the next30minutes, continued Torus temperature rise will:
A. beprevented byplacing one loopofTorus Cooling inservice ONLY.
B. beprevented byplacing both loops ofTorus Cooling inservice.
C. NOIbeprevented unless reactor power is reducedtoapproximately 25%regardless of Torus Cooling alignment.
D. NDIbeprevented while the plant isatpower regardless ofTorus Cooling alignment.
Answer: D Answer'Explanation .
P . .
Choice BasisorJustification Correct:D Theplant mustbeshutdown anddepressurized toprevent the Torus from continuin toheat u .
DistractorsA SRVheat input exceeds Torus Cooling capacity whetherone orbothloops are placed inservice. Plausible ifthe candidate does notunderstand the relationshipbetween theheat addition form thecoreandthe ability ofRHR toremove heat.
B SRVheat input exceeds TorusCooling capacity whether oneorbothloops are placed inservice. Plausible ifthe candidate does not understand the relationshipbetween theheat addition form thecoreandthe ability ofRHR toremove heat.
C reducing power willonly slightly lower pressure andisaccomplished totry andshut the SRV.It does notreduce theheat inputofanopenSRV.Heat inputismorea function ofRPVpressure than power. Plausible the if candidate does notunderstand therelationship between theheat addition form thecore andthe abilit ofRHRtoremove heat.
Page: 145of214 16March2020
m x e =
S A s 2020NRCROExamrev0 Test ID: 330066 Question 54;lnfo AL A Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 1.00 S stemID: 994305 User-Defined ID: ILT-1540-4-011 Cross Reference Number: 295026EA1.01 To ic: ILT-1540-4-011-OT-114 NumField 1:
NumField 2:
Text Field:
Comments:
Psychometrics Level of Difficulty Time Allowance RO Knowledge (minutes)
HIGH 10CRF55.41(b)
(8)
Source Documentation Source: NewExamitem Previous NRCExam Modified Bank OtherExam Bank X ILT ExamBank Reference(s): OT-114 bases Learning PLOT 1540-4 Objective:
K/A System:295026 Suppression Pool HighImportance; Water Temperature RO/
SRO 4.2/4.4 K/A G2.2.44 Abilitytointerpret control room Statement: indications toverify thestatus andoperation ofa system, andunderstand howoperator actions anddirectives affect plant andsystem conditions.
REQUIRED None MATERIALS:
Notes and This question meets theK/A asthe candidate has Comments: tointerpret with theSRVfull open, Torus temperature willcontinue torise regardless of cooling alignment. Thiswould bedifferent if the SRVwere just partially open.
Page: 146of214 16March2020
2020NRCROExamrev0 Test ID: 330066 20%WEAfflifff3FS2%AW3$$$#fAW$iWW$ff74dff22Adf#i5/f8111614$
2isat15%power Unit when anevent occurs. Current plantconditions include thefollowing:
= Reactor waterlevel lowered to+5inches andis currently+10inches rising slowly.
e Reactor pressure is 1095 psig andsteady.
e Reactor power isdownscale onAPRMs.
= Drywell pressure is1.7 psig andrising slowly.
a Drywellaverage temperature is1420 F andrising slowly.
- Toruswater levelis15.2 feet and rising slowly.
= Torustemperature is820 F and rising slowly.
a Annunciator 215D-2, "REACBLDG EQUIPMENT DRAINSUMPHI HILEVEL", -
isinalarm.
Which oneofthefollowing listsALLtheEmergency Operating Procedures(Trip Procedures) thatare tobeentered required based oncurrent conditions?
A. T-101 "RPVControl" andT-102 "Primary Containment Control" B. T-101 "RPVControl" andT-103 "SecondaryContainment Control" C. T-100 "SCRAM" andT-102 "Primary ContainmentControl" D. T-100 "SCRAM" andT-103 "Secondary Containment Control" Answer: A Answer Explanation Choice Basis orJustification Correct: A T-101 entry isrequired duetoReactor pressure above 1085 psig.
T-102 entry isrequired duetoTorus water level above 14.9'. T-103 entry isnot required.
Distracters: B First part iscorrect.
T-103 entry isnotrequired. Plausible because therelated Annunciator for hi-hi floordrain sumpwater level would require T-103
-.----.----.-.... entrr---- . -------- ---------- -------
C Plausible asT-100 isentered under mostlowpower scrams asthe
+1entry condition intoT-101 isnotmet.However, T-101entry is required duetoReactor pressure above 1085 psig.
Second partiscorrect.
D Plausible asT-100 isentered under mostlow power scrams asthe
+1entry condition intoT-101 isnotmet.However, T-101entry is required duetoReactor pressure above 1085 psig.
T-103 entry isnotrequired. Plausible because therelated Annunciator for hi-hi floordrain sumpwater level would require T-103 ent .
Page: 147of214 16March 2020
2020NRCROExamrev0 Test lD: 330066 Questiort 55thfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toCom lete: 0 Difficult : 0.00 S stemID: 2130987 User-Defined ID: ILT-1560-1-6 Cross Reference Number: 2950252.2.4 .
Topic: ILT- 560-1-6 Assess T-102, T-101, andT-103 entry rements NumField 1:
NumField 2:
Text Field:
Page: 148of214 16March 2020
2020NRCROExamrevo Test ID: 330066 Comments: ,iF3MWAM$if(f(Mitf'$None
[;' None F
i"" None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(10)
Source Documentation Source: New Modifi ILT Other Previo ed Bank Bank us2 X NRC (16496 Exams 23)
Reference(s): T-101, T-102, T-103, T-104 Learning PLOT-1560-6 Ob'ective:
K/ASystem:295025 High Reactor Importance:
Pressure RO /SRO 4.5/4.7 K/A G2.2.4 Ability torecognize abnormal Statement: indications forsystem operating parameters thatareentry-level conditionsfor emergency andabnormal o eratin rocedures.
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 149of214 16March 2020
OrjiAm t
&fff////fN/NfN//////////fARMiiiVfffMfffff/////ff//NfffAiffWAA Unit 2hasexperienced a transient with the following:
a Reactor water level is+5" andrising slowly.
= Reactor pressure is 1095 psigandsteady.
a Reactor poweris downscale onAPRMs.
a Drywell pressure is 1.7 psig andrising slowly.
= Drywell average temperature is1420F andrising slowly.
= Torus water level is 15.2' andrising slowly.
Torus temperature is820F andrising slowly.
a Annunciator 215 D-2, REACBLDG EQUIPMENT DRAINSUMPHI HILEVEL, isinalarm.
Which oneofthe following lists the Emergency Operating Procedures that tobeentered arerequired based oncurrent conditions?
A. T-101, RPVControl,and T-102, Primary Control, Containment only B. T-101, RPVControl, andT-103, Secondary Containment only Control, C. T-102, Primary Containment Control, andT-103,SecondaryContainment Control, only D. T-101, RPVControl, T-102, PrimaryContainment Control, Secondary andT-103, Containment Control Answer: A PB-OPS-EXAM-ILT-2015 Page: 1of4 12March 2020 Current View
Choice Basis orJustification
, Correct: A T-101 entryisrequired duetoReactor pressure above 1085 psig.
T-102 entryisrequired duetoTorus water level above 14.9'. T-103 entry isnotrequired.
Distracters: B T-102 entryisrequired duetoTorus water level above 14.9'.
Plausible because multiple conditions other areelevated but below the T-102 entry condition. T-103 isnot entry required. Plausible because therelated Annunciator for hi-hi floor drain sumpwater level would T-103 require entry.
C T-101 entryisrequired duetoReactor pressure above 1085 psig.
Plausible because Reactor water is level above the entry condition andDrywell pressure isbelow theentry condition. T-103 entryisnot required. Plausible because therelated Annunciator for hi-hifloor drain sump water levelwould require T-103 entry.
D T-103 entry isnotrequired. because Plausible therelated Annunciator for hi-hifloordrainsumpwater levelwould requireT-103 entry.
Ps chometrics Level of Difficulty TimeAllowance RO Knowled e minutes Memory 3 3 10CFR55.41(b)(10)
Source Documentation Source: New ModifiedILTBank Other Previous NRC X Bank Exam Reference(s): T-101, T-102,T-103, T-104 Learnin PLOT 1560, Ob'ective: -
1 K/ASystem: 295025 HighReactor Pressure Importance: RO/SRO 4.5/4.7 K/AStatement: G2.2.4 Ability torecognize abnormalindicationsfor system operating parameters thatare entry-levelconditions for emergency and abnormal o eratin rocedures.
REQUIRED None MATERIALS:
Notes and None Comments:
PB-OPS-EXAM-ILT-2015 Page:2of4 12March2020 Current View
f'@W/M$@@dfd@3f!@dfd@33M3Wf@d@3 Question T e: Multi leChoice Status:
Alwasselect ontest? No Authorized forractice? No Points: 1.00 Time toCom lete: 0 Difficul : 0.00 m
== mewmm mea- es--, x-ec m m mr-mor=c wo,2nm S stemID: 1649623 User-Defined ID:
Cross Reference Number:
mammmo-arwmammamemmamnarmaw,aaammemammnm 2.4.1 me To ic: Assess T-101,T-102, andT-103 ent reuirements NumField 1:
NumField 2: A NRC Text Field:
Comments: None None None None Psychometrics Levelof Difficulty Time Allowance RO Knowledge (minutes)
HIGH 10CFR55.41(b)
(10)
Source Documentation Source: NewExamitem X Previous NRC Exam (2017)
Modified Bank Other Exam Bank X ILT ExamBank (2114943)
Reference(s): T-101, T-102, T-103 Learning PLOT-1560 1 Objective:
K/A System: Importance; RO 4.6 K/A 2.4.1Knowledge ofEOPentry conditions and Statement: immediate action steps.
REQUIREDNONE MATERIALS:
Notesand Comments:
PB-OPS-EXAM-lLT-2015 Page:3of4 12March 2020 CurrentView
objective(s):
Associated 1.State TRIPentry the andimmediate conditions steps.
action PB-OPS-EXAM-ILT-2015 4 of4 Page: 12March 2020 Current View
2020NRCROExamrev0 Test ID:330066 j$4i
?/d$if@dffdhAXF/WPf#3k@EMW//27fbf?/2if#/23%)i#jkfi 7/if#5fflBAiW Unit 2isat100% power whenthe SROdirects performance ofGP-4. Current include conditions plant the following:
- ReactorModeswitch is inSHUTDOWN
- Scram pushbuttons have been depressed
- ARIisARMED anddepressed
- scram All blue areOFF lights
- All controlrods arestill intheiroriginal positions ofthe Which is following theFASTEST method for theUROtoinsert ofcontrol all rods?
A. De-energize allthe scram soleniods IAWT-213, "Scram Solenoid Deenergization".
B. Raise CRDcooling water DpIAWT-246, "Maximizing CRDFlow totheReactor Vessel".
C. Vent the CRDwithdraw line IAWT-215, "Control RodInsertion byWithdrawLine Venting".
D. Manually insert thecontrol rods IAWT-220, "Driving Control Failure RodsDuring to Scram".
Answer: A Page: 150of214 16March 2020
t 2020NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: A Theconditions show anelectric that ATWSoccurred atrated power, andnocontrol rods changed position. Allofthe methods listed in Answers A-Dare actualmethods toinsert control rods. Someofthe listedmethods areappropriate foranelectric ATWSandsome methods are appropriate fora hydraulic ATWS,andsomecanbe used for either type ofATWS.
De-energizing the scramsolenoids, which isappropriate for anelectric ATWS, can beperformed byplacing allCRDscram test switches (located in a single control roompanel) intheDOWNorscram position. This can beperformed very quickly bytheUROand represents thefastest method toinsert control rods IAWT-213.
Answer A is correct.
Distractors: B This answer plausiblesince it hasATWSactions. Raising CRD cooling water procedure(T-246) requires the EOtoopen several valves inthe plant, the standby CRDdrive place water filter inservice, secure recirc seal purgeandmanually openthe CRDFCV,anddirect theEOtosecure CRDcharging water. Thisis not thefastest method toinsert the control Answer rods. B is incorrect.
C This answer plausible sinceithasATWS actions. Venting theCRD withdraw linemaybeperformed for bothan electric andhydraulic ATWS.Venting the CRDwithdraw line IAWT-215 requires that avent capberemoved atanHCUandasingle vent line be attached toa withdrawn control rodHCU.Thenthe withdraw line valve is manually opened. These actions arethen duplicated ateachHCU thathasa withdrawn control This rod. isnotthe fastest method to insert the control rods. Answer C isincorrect.
D This answer plausible sinceithasATWSactions. Manuallyinserting control rods IAWT-220 isapplicable toboth anelectric andhydraulic ATWS.This requires thattheCRDFCVbeplaced inManual and opened andthe EOwill close the CRDcharging water valve. TheURO thenbypasses theRWMandthenbegins selecting a control rodand inserting with RMCS.Eachcontrol rodwill have tobeselected and inserted. This isnotthe fastest method toinsert thecontrol rods.
Answer D isincorrect.
Page: 151of214 16March2020
/i 2020 NRCROExamrevo Test 330066 ID:
Questioni56info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2130038 User-Defined ID:
Cross Reference Number: .. .
To ic: 3.Describe the s m tom-based TRIPmiti ation strateies.
NumField 1:
NumField 2:
Text Field:
Page:152of214 16March 2020
j 2020NRCROExamrev0 Test ID: 330066 Comments: FAWA 7'$gliiEg 7"#fftt"d$ None None yggyg~~:;,;ygg etryc/~;TTW None None Pschometrics Level of RO Knowled e High 10CFR55.41(b)(5)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): T-101, T-213,T-246, T-215, T-220 Learning PLOT 1560, -
3 Ob'ective:
K/ASystem:295037 SCRAM Condition Importance:
Present andReactor RO /SRO Power AboveAPRM 4.4/4.7 Downscale orUnknown K/A G2.1.7 Ability toevaluate plantperformance Statement:andmakeoperational judgments basedon operating characteristics, reactor behavior, andinstrument inter retation.
REQUIRED None MATERIALS:
Notesand None Comments:
Page: 153of214 16March 2020
2020 NRCROExamrev0 Test ID: 330066 0' '
'"Mffhfkff&fi?kV?WiWJAWA$WsFf&%Whfffhfifkki$kkfb)fkflBl%df$
Unit 2isat100%power, whenanevent occurs with thetimeline below:
0800 Annunciator 210 F-2, "DRYWELL HI-LO PRESS" alarms 0800 Drywell pressureis at 0.75 psig andrising 0801 OT-101, "High Drywell Pressure" hasbeen directed 0802 "C" Drywell Chiller isstarted 0803 Drywell pressure is1.2psig and risingslowly 0803 GP-4 "Manual Reactor Scram 0804 AII controlrods inserted andfeedwater iscontrolling RPVwater levelat23inches 0805 AII scram actions complete IAWtheir respective RRCs 0807 Thefollowing plant indications thenappear:
- Annunciator 210- F-1, DRYWELL HIPRESS TRIPalarms a Annunciators E1DIESEL RUNNING,E2 DIESEL RUNNING; E3DIESEL E4DIESEL RUNNING, RUNNING alarms a pressure Drywell isnowsteady Which ofthefollowing states the plantconditions over thenext 2 minutes? (Assume NOfurther operator actions) 1 Theemergency diesel generators arerunning withoutput breakers closed
- 2. RPVwater level willrise above 23inches
- 3. CSTwater level willlower
- 4. All DRYWELL COOLER FansandDWCHILLERS indicate redlights ON A. 1and3 ONLY B. 1and4 ONLY C. 2 and3 ONLY D. 2and4 ONLY Answer: C Page: 154of214 16March 2020
'i 2020 NRCROExamrev0 Test ID: 330066 Justification: Choice Basis'or Justification Correct: C Unit 2wasatrated power whendrywell pressure began torise and T-101 wasentered. DWpressure continued torise the theoperator manually scrammed the All plant. scram actions have been performed andfeedwateriscontrolling RPVwater andis level, stable at23 inches. Minutes later, indications are provided that DWpressure has risen to/past 2 psig.
When 2 psig DWpressure isreached, a scram signal isapplied, high pressure coolant injection (HPCI)(with a starts suction from the condensate storage tank, CST) andinjects into RPV the until anRPV water levelsignal high of46inches trips theHPCI turbine. Since the HPCIpump off istaking a suction the CST could (but thetorusbe asa andis suction), injecting the regardless into RPV, offeedwater level controls, CSTwater level will drop and RPVwater level willriseabove the feedwater level control setpoint of23inches. Thus answer options 2and3 are correct. OnlyAnswer C selects these choices andis correct.
1 Plausible asona DWhigh pressure of 2psig, all 4 emergency diesels startbut remain unloaded with their outputbreakers open until a loss ofpower issensed. Since the diesel generators areproducing 0 var and0watts generators have (no reactive nocurrent load power andnoreal load), thediesel factor.
4.Plausible because at2psig DWpressure, all DW Cooler Fans trip, but theDWChillers remain operating andthecandidate may misinterpret theisolation logic.Thechillers remain energized (red on) lightswhile only thecooler fans trip (green lights on).
Distractors: A This answer isplausible if the candidate misinterprets automatic actions ona Drywell pressure of2 psig. Seeabove forreason 1 being wrong.
B This answer isplausible if thecandidate misinterprets automatic actions ona Drywell pressure of2 psig. Seeabove forreasons 1and 4 being wrong.
D This answer isplausible if thecandidate misinterprets automatic actions ona Drywell pressure of2 psig. Seeabove forreason 4 being wrong.
Page: 155of214 16March2020
7 =
2020 NRCROExamrev0 Test ID: 330066 Question 571nfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficul : 0.00 S stemID: 2130092 User-Defined ID:
Cross Reference Number; Topic: 3g.Describe the High Coolant Pressure injection System desi nfeature s and/or s andf interlock NumField 1:
NumField 2:
Text Field:
Page: 156of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 Comments: iii$fM/97X$lf?'"T%NYT(ffiBi None None None Pschometrics Level of RO Knowled e High 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT OtherPrevio X ed Bank Bank us2 NRC Exams Reference(s): PLOT-5023, 3 Learning PLOT 5023,3g -
Ob'ective:
K/ASystem:295024 High Drywell Importance:
Pressure RO / SRO 4.1/4.0 K/A EA1.01 Ability tooperate and/or monitor the Statement: following as they apply toHIGHDRYWELL PRESSURE:
HPCI REQUIRED None MATERIALS:
Notes and None Comments:
Page: 157of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 EbdfWGdffitffhYkW4WfffWrdfM4WWff/WMf%d$fiff%SAi 2isat100%power when a reactor Unit scram occurs.
ofRPVwaterlevel isshown asfollows:
Theplot TimeT initial
= time of the scram a TimeT final= approximately 2 minutes after the scram TheSROhasdirected anRPVwater level bandof+5inches to+35inches IAWT-101, "RPVControl".
gy r - .-,.-...... .........-.-.-.-.- .-....-. -.-..-...- -
- y -
x g t
g .-..--.------- ---..-. .....-.-.- ...--..-~ -
C-o-.-
a I
a I
g .
A a J I RPVWater Level 4 A-O - -- - - ' - - ---'- ---- - - --
(inches) a I
g I g I I
-20 =- ----+ - ---------
g
/ :
4 j -.----...4,-.- - .-.- -.- -.- --..-----..---.- ---.
3 A I I g p ...
1 +. -
I I Tinities Time Tw Whichofthe following describe the correct operator action toestablish RPVwater level inthedirected band?
A. AtPoint 1onthe graph: ThePlant Reactor Operator will verify HPCIinjection the into RPVatthe 20C004B ECCSPanel B. AtPoint 2 onthe graph: TheUnit Reactor Operator will manually trip all3feedwater pumps with the trip pushbuttons atthe 20C005 Panel C. AtPoint 3onthe graph: Oncethe Unit Reactor Operator reports they have controlof RPVwater level with feedwater, thePlant Reactor Operator should shutdown theHPCI system atthe 20C004B ECCSPanel D. AtPoint 4 onthe graph: ThePlant Reactor Operator will manually place theRCICFlow Controller toOatthe 20C004C ECCSPanel Page: 158of214 16March 2020
m, = ,
2020NRCROExamrev0 Test ID: 330066 Answer: C Answe'r Explanation .. . .... .
Justification: Choice Basis orJustification Correct: C The graph shows RPVwater levelfollowing a scram. Answer C states that the operator hascontrol ofRPVwater levelwith thefeedwater system at Point 3,andthat other injection systems mayberemoved.
Both HPCI andRCIC auto started whenRPVwater leveldropped to
-48inches. These systems cannowbesecured once control ofRPV water level with feedwater (even though water level atPoint 3 islower then the normal setpoint, and islow inthe band) is v erified,andwater level isabovethe low waterinitiating setpoint for HPCl/RCIC. Answer Distract'of A This erisplausiblesince HPCI wiifaiito start ona lowPsPV water level.Answer A says that the operator will verify HPCIinjection into the RPVatPoint 1.HPCIwillauto start andinject into theRPVona RPV water level of-48 inches. Point 1 is atabout -28inches andisabove theHPCI auto initiationsetpoint and HPCI will notyet have auto started andrunning and.i..njecting.Answer A is incorrect.
B This answer isplausible since the operators dotake controlof feedwater whenRPVlevel begins torecover. Answer B says totrip all 3feedwater pumps atPoint 2.Point 2 is where it shows that RPV water level isrecovering andisstarting torise. RRC 94.1-2, "Reactor Operator Scram Actions", directs the operator to emergency stop all feedwater pumps whenRPVwater level begins to recover. Thus, Point 3would bethe pointwhenthe operator emergency stops the feedwater pumps- not trips thepumps. Answer B isincorrect.
D This answer isplausible since RCICwill beinjecting. When RPV water reaches +46inches, aturbine steam admission valve will auto close, andwill then re-open whenRPVwater goes lowagain -48inches. This Point 4 is above the setpoint forthe steam valve toclose, essentially preventing anyinjection flow. Since there isalready noRCICflow, there isnorequirement toclose theRCICflow control valve (which would stop injection flow). Answer D isincorrect.
Page: 159of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Question58IAfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized ractice?
for No Points: 1.00 TimetoCom lete: 0 Difficult: 0.00 S stemID: 2130150 User-Defined ID:
Cross Reference Number:
Topic:
. 2.Discuss system setpoints/interlocks andautomatic actions associated with TRIP ent conditions.
NumField 1:
NumField 2:
Text Field:
Page: 160of214 16March 2020
s:. , , , , , , , , , ,
2020NRCROExamrev0 Test ID: 330066 Comments: EENiFE##E'fff4$feriff"'f giifeV($jiiit None P None None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT OtherPrevio X ed Bank Bank us2 NRC Exams Reference(s): PLOT-PBIG-2100 Leaming PLOT PBlG-2100,2 -
Ob~ective:
K/ASystem:295031 Reactor Low Importance:
Water Level RO /SRO 4.4/4.0 K/A G2.1.30 Ability tolocate andoperate Statement: com onents, includin local controls.
REQUIRED embedded text MATERIALS:
Notes and None Comments:
Page: 161of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Theintended order ADS valvesare manually opened inaccordance with T-100 "SCRAM" is (1)?
This isdone to (2) .
A. (1) A,B, C, G,K (2) evenlydistribute heat into the Torus B. (1) A,B,C,G,K (2) prevent opening Torus toDrywell vacuum breakers C. (1) A,B,K,C,G (2) evenly distribute heat into the Torus D. (1) A,B,K,C,G (2) prevent opening Torus toDrywell vacuum breakers Answer: C Answer Explanation" Justification: Basisor Justification Choice Correct:C T-100 directstheoperator to"DistributeHeat Evenly in the Torus." Above theADSvalves isa ta the the directs o enin se uence.
Distractors A Plausible ifthecandidate doesnotremember the opening sequence.
ABCGKisthe order given inthememory aid usedto remember which SRVsare ADSvalves.
Correct reason is iven.
B Plausible ifthe candidate does notremember the openingsequence.
ABCGK isthe order given inthememory aid used toremember which SRVsare ADSvalves. Plausibleifthe candidate believes thatopening a Vacuum breaker isanissue. An open vacuum breaker isonlyanissue if thevalve does notreset.
D Opening sequence iscorrect.
Plausibleifthecandidate believesthat opening a Vacuumbreaker isan issue. Ano envacuum breaker isonlanissue ifthe valvedoes not reset.
Page:162of214 16March 2020
E 2020NRCROExamrev0 Test 330066 ID:
Question[59!Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: 0.00 S stemID: 2084252 User-Defined ID: B NRC 2019 Cross Reference Number: 295013 AK103 Topic:
. ILT -
5001A-9c. procedures Foridentified with associatedthe Main Steam and PressureRelief NumField 1:
NumField 2:
Text Field:
Page: 163of214 16March 2020
2020NRCROExamrevo Test 330066 ID:
Comments:
BEff F*(fffT*$"'($)AjjjiT/(fffj None
$lfff(ffC',~','T'(((fffff(ff Wfifj fffff///fffA lf None fjf($(((ff(f[((ffffjj EI'Ej'[ffff(((ff None PA1WT/ffj None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(10)
Source Documentation Source: New Modifi ILT OtherPrevio ed Bank Bank us2 NRC x Exams (21154 X
- 55) (2019)
Reference(s): RRC 1G.2 Learning PLOT5001A-9c -
Ob'ective:
K/A 295013 Importance; RO/SRO Sys High 3.0/3.3 tem Suppressi onPool Temperat ure K/A AK1.03Knowledge ofthe operational Statement: implicationsofthe following concepts asthey apply toHIGHSUPPRESSION POOL TEMPERATURE :Localized heatin REQUIRED None MATERIALS:
Notes and This questionmeetstheK/Abecause Comments: consideration mustbegiven inaccordance withtheRapid Response Card toprevent localizedheating byopeningupthe SRV's in a certainorder.
Page: 164of214 16March 2020
w w, ,
x 2020NRCROExamrev0 Test ID: 330066
$%%j5&$@$3$d97117/f#2FM@MDD?/d21@1D$h3%
Thefollowing conditions existonUnit 3:
a Reactorscrammed due tolow RPVwater level.
a Reactorpower is50%.
a RPVwater level isbeing controlled between -60to-100 inches.
= 135controlrods did NOTinsert.
a All scram valves areopen.
Inaccordancewith T-101, "RPVControl", and the referencedT-200 series procedures, select the below statement which identifiesthe proper operator actions needed toinsert the remaining control rods.
A. Isolate instrument airtothe scram air headerand then vent the scram air header.
B. Maximize CRDFlow totheReactor AND manually insert controlrods concurrently C. Bypass andreset both ARIandscram signals and openSDVvents When anddrains.
appropriate, insert a manual scram.
D. OpenHV-3-03-56, "Charging WtrHdrBlk Vv", bypass the RWM,then manuallyinsert control rods using the "Emergency In/Notch Override" switch.
Answer: C Page: 165of214 16March 2020
n 2020NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: C Thequestion stemshows that a hydraulicATWShasoccurred as evidencedbyreactor power at50%andall scram valves areopen.
T-101, RPVControl, lists several methods toinsertcontrol rods, depending onwhat type ofATWS:electric orhydraulic.
T-216-3 for bypassing/resetting ARIandscram, andopening SDV vents/drains, isonemethod toinsert controlrods fora hydraulic ATWS. This will close all scram valves andwillallow the CRD hydraulic system torecharge the CRDaccumulators, plus itallowsthe scram discharge volumetodrain. Whenthe scram airheader is re-pressurized and the SDVis drained, thenanother scram is manually input.
Distractors: A This answer isplausible since thisisanactio-'nforanelectric ATWS, however, since thescram air header isalready de-pressurized as evidenced bythe open scram valves, venting the scram airheader is notnecessart . .
B This answer isplausible since maximizing CRDflow tothe reactor vessel andmanually insertingcontrol rods are actionsfor a hydraulic ATWS,however they cannot beperformed concurrently inaccordance with T-246 CRD "MaximE FLowto the Reactor Vessel" D Driving control rods isalways aneffective method toinsert controlrods regardless ofATWStype. Buttheprocedure requires closing the CRD charging scram water valve andARIsignal not isstill (or openingopening the CRDFCV).
induetotheRPV water levelbeing A
controlled atbelow the scram setpoint forRPVwater level, andthus with all scram valves open, allCRDflow isgoing torecharge the CRD accumulators, andultimately into theRPVbecause the scram valves areo en. There isinsufficient flowtomanuall drivecontrol rods.
Page: 166of214 16March2020
- i r 2020NRCROExamrev0 Test ID
- 330066 Questioni60 Mfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 2 Difficult: 2.50 S stemID: 994215 User-Defined ID: A-ILT-1560-12-002 Cross Reference Number: 295015AK2.01 Topic:
. A-ILT-1560-12-002 Thefollowing onUnit conditions exist 3:
- Reactor scrammed duetolowRPVlevel.
NumField 1: 0.00 NumField 2: 0.00 Text Field:
Page: 167of214 16March 2020
2020NRCROExamrev0 TestID:330066 Comments:
i None This questionmeets the K/A byrequiring thecandidate to determine thatthis isa hydraulicATWSandactions related totheCRDhydraulics must betaken tocorrect.
v f None Ps chometrics Levelof RO Knowled e High 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT Other Previo ed Bank Bank us2 X NRC (50814 Exams 2)
Reference(s): T-101, T-214, T-213,T-216, T-220 Learning PLOT 5057 -
2a Ob'ective:
K/ASystem:295015 Incomplete Importance: RO SCRAM /SRO 3.8/3.0 K/A Ak2.01 Knowledge ofthe interrelations Statement:between INCOMPLETE SCRAM andthe followin:CRDh draulics REQ UIRED None MATERIALS:
Notesand None Comments:
168of214 Page: 16March 2020
n ,, =
2020 NRCROExamrev0 Test ID: 330066
$g 774Ajf'7($k#&piQ$p$[fff$jgjpj@@$@ai$%$$fjg[j$&f2d$ jj&,,, NAjifff$pt$j f??f4ff$/kWffk Unit2isat80%power withthe conditions:
following e EHCLoadSet isat80%tolimit Digital Main Turbine loading, whichisexperiencing vibration issuesat all higher loads e EHCPressure Digital Set is setat912 psig e EHCMaxCombined Flow Limitis Digital set at117%
A Positive Reactivity event occurs EHCwill Digital respondbyopening .(1). in response tosensing
, inA arise pressure.
A. 1)Turbine ControlValves 2)Reactor B. 1)Turbine ControlValves 2)PAM C. 1)Bypass Valves 2)Reactor D. 1)Bypass Valves 2)PAM Answer: D Page: 169of214 16March 2020
2020NRCROExamrev0 Test ID:330066 Justification: Choice Basis orJustification Correct: D Digital EHCissetusing Load set tolimit the Load onthe Turbine.
Whena positive reactivity event occurs reactor power will riseand will inturn raise reactor pressure. This inturn willcause a sensed pressurerise inPAM.DEHC willrespond tothis rising pressure by allowing more steam toflow through tolower PAMpressure. Since DEHC is limited bythe load set, itwill not open theTurbine Control Valves further andwill start toopen Bypass valvestoallow more steam flow directlytothecondenser tolower PAMpressure, which will then cause alowergofReactor Pressure.
Distractors: A Plausible because DEHCload set isnormally setat105%andwould allow the Turbine Control Valves toopen during allbut themost limiting pressure transients. This would maintain the bypass valves closed duringmost positive reactivity events.
Plausible asthepositive reactivity event iscausing the reactor pressure torise. However DEHConly responds tothe coresponding PAMpressure rise and not the reactor pressure rise. DEHCis controling PAMpressure and withtheMSIV's open irtelates to Reactor Pressure. IftheMSIV's were closed, DEHCwould still only respond toPAMpressure and not Reactor Pressure.
B Plausible because DEHCload set is normally set at105%andwould allow the Turbine Control Valves toopen during all but themost limiting pressure transients. This would maintain the bypass valves closed during mostpositive reactivity events.
Second Part iscorrect C First part is correct Plausible asthepositive reactivityevent iscausing the reactor pressure torise. However DEHConly responds tothe coresponding PAMpressure andnot rise the reactor pressure rise.DEHC is controling PAMpressure andwith the MSIV's open irtelates to Reactor Pressure. IftheMSlV's were closed, DEHCwould still only resondtoPAM ressure andnotReactor Pressure.
Page: 170of214 16March2020
2020NRCROExamrev0 Test ID:330066 Questione6tInfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficul : 0.00 S stem ID: 2131758 User-Defined ID:
Cross Reference Number: 295007 AK3.06 Topic: 5b.Describe therelationships between theElectro-Hydraulic Control Lo icS stemEHCandthe foil NumField 1:
NumField 2:
Text Field:
Page: 171of214 16March 2020
=,,
2020NRCROExamrevo TestID:
330066 Comments:
f Ps chometrics of Level Diffic Time RO Knowledge ulty Allowance minutes HIGH 10CFR55.41(b)(5)
Source Documentation Source: X New Exam itemPrevious NRC Exam ModifiedBank Other ExamBank ILTExamBank s: PLOT-5001DL Reference Learning PLOT-5001DL-5b Ob'ective:
K/ASystem: 295007High -
Reactor Importance:
Pressure RO /SRO 3.7/3.8 K/AStatement: AK3.06Knowledge ofthereasons for the following responsesasthey apply to HIGH REACTOR PRESSURE: Reactor/turbine ressure reulatin s stemo eration REQUIRED NONE MATERIALS:
and Notes This question meets theK/Aasthe Comments: candidate isquestionedonwhat(reason) theReactor/turbine pressure regulating system isresponding to,andhowit resonds.
Page:
172of214 16March 2020
2020NRCROExamrev0 Test ID:
330066
$gWWg Af$QfWf(($fffyjQin&l$ff$$ffM$og$fg; f?$ffffff#jWiffQfgjQbigligljj$j@i Thefollowing alarms are received onUnit 3:
= 3VENTSTACKRAD MONITOR HITROUBLE A (318 B-5)
. 3VENTSTACKRAD MONITOR HITROUBLE B (318 C-5)
Inaccordance with ON-104, 'Vent Stack High Radiation',whichradiation monitor must bechecked tohelp determine thesource ofthe highradiation?
A. Control Room B. Radwaste Building C. Recombiner Building D. SteamPacking Exhauster Answer: C Answer Explanationn .. e , 1 . ................ . ... . .
Choice BasisorJustification Correct:C IAWON-104, the if Unit3Vent S tackRadiation is high, the Recombiner Buildin exhaust radiation monitor should bechecked.
Distractors A TheControl Roomhasits ownexhaust tothe roof of the control room.
Although the Control Roomventilation exfiltrates tothe turbine buildingand would possibly pass through the Unit3Vent Stack, theradiation monitors for thecontrol roommonitor incomingoutside air andarenot mentioned in ON-104. Plausible if candidate the misinterprets the alignment of the stations ventilation s stem.
B Plausible astheRadwaste Buildingwould bechecked iftheUnit 2 vent stack radmonitor hitrouble cameit.
alarm Thecandidate maymisinterpret the ali nment ofthe station s stem.
ventilation D Plausible astheSteam Packing Exhauster could bea source ofhigh radiation, however it would showupintheMainStack radmonitors. The candidate ma misinter ret thealinment ofthestation ventilation s stem.
Page:173of214 16March2020
2020NRCROExamrev0 Test ID: 330066 Question$2[Info: ....... x ,
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult : 0.00 S stemID: 2130904 User-Defined ID: ILT-1550-1-004 Cross Reference Number: 295017 A1.04 To ic: ILT-1550-1-004 ON-104 execution NumField 1:
NumField 2:
Text Field:
Comments:
[ None fffffff,f'((J'jJT"'fffjffjNone
- None
'g None Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes Memory 10CRF55.41(b) 10 Source Documentation Source: NewExamitem PreviousNRC Exam X Modified Bank(639549) Other ExamBank ILTExamBank Reference s : ON-104 Learning PLOT-1550-1 Ob'ective:
K/ASystem: 295017 Importance; -
RO/
High SRO Off-site 3.6 /3.8 Release Rate K/A A1.04Ability andormonitor tooperate Statement:the following astheyapply toHigh Off-site Release Rate:
Stack-gas monitorin s stem REQUIRED None MATERIALS:
Notes and None Comments:
Page: 174of214 2020 16March
2020NRCROExamrev0 Test ID: 330066 ISAAAW$$$ifkffffjk$kf?fMAf[jiffj$f$ffj5%W[fff)$ibig;JSj!$ffillirdiett Unit2isoperating at100% power
= A fire occurs inthe Unit2 Reactor Building a Secondary Containment Temperatures arerising Whichofthe following describes the level instruments most affected bythe fire andwhy?
A. Narrow Range Instruments due tolong variable leg vertical runs inthe Reactor Building B. Narrow Range Instruments due to longreference leg runs vertical inthe Reactor Building C. WideRange Instruments duetolongvariable leg vertical runs inthe Reactor Building D. WideRange Instruments duetolong reference leg verticalruns intheReactor Building Answer: D Answer ExplanationL' CA C . .......... . ........... .. . . .
Choice Basis orJustification Correct: D T-103 includes atable toreference todetermine whether aninstrument can beused todetermine level. This table uses Reactor Building Temperatures near the reference legs. Listed inthe table areWideRange and Fuel zone instruments. This isbecause oftheir long verticalreferenceleg runs inthe Reactor Buildin which cancause erroneous readin s.
Distractor A Plausible astheNarrow range instruments alsohave instrumentruns inthe s: Reactor building. However theNarrow Range have their longer reference leg vertical runs intheDrywell.
Plausible asthevariable leg will beaffected byhigh temperatures, however thereference legs havethelonger vertical runandwill bemoreaffected by the temerature.
B Plausible astheNarrow range instruments alsohaveinstrument runs inthe Reactor building. However theNarrow Range have their longer reference leg vertical runs intheDrywell andareless affected than the WideRange instruments with elevated Reactor Building temperatures.
Lonreference levertical runs would bea correct answer.
C Widerange instruments iscorrect Plausible asthe variable leg will beaffected byhigh temperatures, however the reference legs have the longer vertical runandwill bemoreaffected by the temerature.
Page: 175of214 16March 2020
i!
2020NRCROExamrev0 Test ID: 330066
.Question 63info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 1 Difficult: 1.00 S stemID: 2131426 User-Defined ID: ILT-5002B-5F-003 Cross Reference Number: 295032 EA2.02 To ic: ILT-5002B-4f-003 hihreactor buildin tem NumField 1:
NumField 2: N/A Text Field: A Comments:
Psychometrics Level of Difficulty TimeAllowance RO Knowledge (minutes)
MEMORY 10CRF55.41(b)
(2)
Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other Exam Bank ILT ExamBank Reference(s): PLOT-5002B, T-103 Learning PLOT5002-4f Objective:
K/A System: 295032- High Secondary Importance; Containment Area RO/
Temperature SRO 3.8/3.5 K/A EA2.02 -
Ability todetermine and/orinterpretthe Statement:following asthey apply toHigh Secondary Containment Area Temperature: Equipment operability REQUIREDNone MATERIALS:
Notes and This question meetsthe K/A asthe candidatewill Comments: bedetermining which equipment'sability to perform bemostaffected will byHigh Secondary Containment Area Temperatures.
Page:176of214 16March 2020
- C 1::::,,
. ::::: 1:'::::::
2020NRCROExamrev0 TestID:330066 41%Uf&15(i fidf&ffififffMAMifffdWidibWdlffJD$21FJ$$Aa Unit2 conditionsare asfollows:
= 10%power and925 psig during a startup e CRDPump2Atagged out for emergent repair
= Annunciator CRDACCUMULATOR LO-PRESSHILEVELisinalarm forasingle withdrawn control rod 3minutes later,the followingannunciators andindicationsarereceived:
a B CRDWATERPUMPOVLD(211 G-2) a B CRDWATERPUMPTRIP (211 G-1) a CRDHYDRAULIC HITEMP(211 G-5)
= CRDCharging Header pressure is930psigand lowering a A second accumulator trouble alarm onawithdrawn control rod Which ofthe followingstates the next requiredaction IAW ON-107, "Loss ofCRDRegulating Function",
andthereason for thisaction?
A. Scram the reactor immediately, toensure control rods canbeinserted before theHCU accumulators depressurize and cannot complete the scram.
B. Scram the reactor immediately, toprotect control rods drive sealsandbushings from damage due tohigh temperature C. RESTORE charging header pressure togreater than 940psig within 20 minutes, or Scram thereactor, toensure control rods canbeinserted before theHCUaccumulators depressurize and cannot complete thescram.
D. RESTORE charging header pressure togreater than 940psig within 20minutes, or Scram the reactor, toprotect control rods drive sealsandbushings from damage duetohigh temperature Answer: C 177of214 Page: 16March2020
t 2020NRCROExamrev0 Test ID: 330066 Justification: Choice Basis orJustification Correct: C Thequestion shows that during astartup with a single CRDpump tagged out for repair, the only remaining CRDpumptrips andall CRDheader pressure islost, anda second CRDHCUtrouble alarm hascomein. Italso shows that CRDcharging header pressure has lowered tobelow 940psig. With reactor pressure greater than 900 psig, ON-107requires a manual scram after 20minutes. IAWTS Bases 3.1.5, "The control rod scram accumulators are part ofthe Control RodDrive (CRD) System andareprovided toensure that thecontrol rods scram under varying reactor conditions. Thecontrol rod scram accumulators store energy sufficient tofully insert a control rod at any reactorvessel pressure. "
Thus, theHCU accumulators must beable toscram control rods before HCU accumulator pressure becomes too low.
Distractors: A Plausible because if reactor pressurewasless than 900psig, with other listed conditions ON-107 would require animmediate scram.
Second part iscorrect B Plausible because ifreactor pressure wasless than 900psig, with other listed conditions ON-107 would requireanimmediate scram.
Plausible because ON-107 refers to a loss ofCRDcooling leading tooverheating ofthe driveseals and bushings. ON-107 will alsocall for a scram tobeperformed onavalid CRD high temperature, however the operators have onehour to correct the high temperature before the scram isrequired.
D First part iscorrect Plausible because ON-107 refers toa loss ofCRD cooling leading tooverheating ofthe driveseals andbushings. ON-107 will alsocall for a scram tobeperformed onavalid CRDhigh temperature, however theoperators have onehour tocorrect thehigh temerature before the scram isreuired.
Page: 178of214 16March 2020
j 2020NRCROExamrev0 Test ID:330066 Question 64!Info .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toCom lete: O Difficul : 0.00 S stemID: 2130530 User-Defined ID:
Cross Reference Number: 2.4.21 To ic: ON-107 when andwh toscram NumField 1:
NumField 2:
Text Field:
Page:179of214 16March 2020
.n mm, ,, e n
2020NRCROExamrev0 Test ID: 330066 Comments: r2iff///ffl$RiW((((((("9'T"i$l(((filiBj$ None F/ None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(7)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): ON-107 Learning PLOT DIG-1540, -
7 Ob'ective:
K/ASystem:295022Loss -
ofCRD Importance:
Pumps RO/SRO 4.0/4.6 K/A G2.4.21 Knowledge oftheparameters and Statement:logic used toassess thestatus ofsafety functions, such asreactivity control, core cooling andheat removal, reactor coolant system integrity,containment conditions, radioactivit release control, etc.
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 180of214 16March 2020
- :.: x ::
TEeGL . .
2020NRCROExamrev0 Test ID: 330066 4llid[AW%2Ffk)33ff@WS2WWWW$3h3fj$h$@$$$$fh4$
Unit 2isat100% power whenDrywell conditions began todegrade. Current conditions areasfollows:
a Drywell Bulk Average Temperature is149*F andrising slowly a Drywell pressure is1.3 psig andrising slowly T-101,"RPVControl" and T-102, "PrimaryContainment Control" have been entered a ALLReactor Operator and Plant Reactor Operator actions arecomplete forthereactor scram a RPVwater levelis23inches and steady Which ofthefollowing istherequiredoperator action with regards tomonitoring containment conditions?
A. Continue tomonitor Primary Containment hydrogen andoxygen using CAC.Report whenPrimary Containment hydrogen reaches 0.5% tore-enter T-102.
B. Continue tomonitor Primary Containment hydrogen and oxygen using CAC.Report whenPrimary Containment oxygen reaches 0.5%tore-enter T-102.
C. Place CADModeinservice inaccordancewith theRapid Response Card andmonitor Primary Containment hydrogen andoxygen.Report whenPrimary Containment hydrogen reaches 0.5% tore-enter T-102.
D. Place CADModeinservice inaccordance with theRapid Response Card andmonitor Primary Containment hydrogen andoxygen. Report when Primary Containment oxygen reaches 0.5% tore-enter T-102.
Answer: C Answer;Explanationn, iCA n3 n nnsCLE Justification: Choice Basis orJustification Correct: C T-102 says tomonitor PChydrogen andoxygen levels.The question shows degraded conditions inthe Drywell. Following a manual scram (where RPVwater level goes below aGroup IIIisolation setpoint of+1 inch.).Whenthis isolation occurs, theCACsystem isolatesandthere isnoH2/O2 monitoring inservice. CADmodecanthen beplaced in service using theRRC.If hydrogen reaches 0.5%, then theROwill report this value asa re-entry into T-102.
....A Distractors: Thisanswer isplausible if the candidate misinterprets RPVwater level response from a scram at100%power. Ifthere wasnoCACisolation, thisanswer would becorrect.
Second part iscorrect B This answer isplausible ifthe candidate misinterprets RPVwater level response from a scram at100%power andthe CACisolation.
Plausible since the gasleg directs monitoring both hydrogen and oxygen, misinterpretation could leadtothinking thatoxygen, instead of hydrogen, hasanyactionable steps inthe gasleg.
D Thefirst part iscorrect Thesecond part isplausible since thegasleg directs monitoring both hydrogen andoxygen, andmisinterpretation could lead tothinking that ox en,instead ofh droen,hasan actionable stesintheasle Page: 181of214 16March 2020
2020NRCROExamrevo Test ID: 330066 Question65htfoAme :
Question T e: Multi leChoice Status: Active Alwasselecton test? No Authorized forractice? No Points: 1.00 Time toComlete: 0 Difficult
- 0.00 S stemID: 2130953 User-Defined ID:
Cross Reference Number: 500000 EK3.01 Topic: PBIG-2102-4. State T-102, the Containment Primary Control terms and definitions. G.2.4.17 NumField 1:
NumField 2:
TextField:
Page: 182of214 16March 2020
x:::::::::m::: :1 s:e= . y x ~
2020NRCROExamrevo Test ID: 330066 Comments: None iii""" None r///j/7/AWSt~ %T'C
'""'"'#"f'ff'U f"W None
===-----=-.. ..----
Pschometrics Level of RO Knowled e High 10CFR55.41(b)(5)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): T-102, T-102-BASES Learning PLOT PBIG-2102, 4 -
Ob'ective:
K/ASystem:500000 High Containment Importance:
Hydrogen Concentration RO /SRO 2.9/3.3 K/A EK3.1 Knowledge ofthereasonsfor the Statement:following responses asthey apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: of Initiation containment atmoshere control s stem REQUIRED None MATERIALS:
Notes and While the conditions donotcurrently indicate Comments: High Containment Hydrogen Concentration.
TheK/Aismetasthe conditions given required theCADsystem tobeinitiated
/placed inservice torestore sampling, specifically fortheidentification rising /High Containment H droenConcentration.
Page: 183of214 16March2020
uJ 7 ,.~
7 7 2020NRCROExamrev0 Test ID: 330066
$0W@Af$f%MfffWf)fffWkhWf@2W@Wh$@$5 Youhave been tasked with coordinating awalkdown foranupcoming inspection. Thewalkdown requires useoftheMaster Security Key/SE-10 the key.
Which ofthe following states thekeycabinet that contains the necessary keys?
A. Shift Manager (SM) keycabinet ONLY.
B. Shift Operations Assistant (SOA)keycabinet ONLY.
C. WorkExecution Center Supervisor (WECS) keycabinet ONLY.
D. Shift Operations Assistant (SOA) keycabinet AND WorkExecution Center Supervisor (WECS) key cabinet Answer: A Answer;ExplanationT PME EfPA CE WAkLn Justification: Choice BasisorJustification Correct: A IAWRT-O-100-960-2, the Security Key/SE-10 Master keyisfound only inthe ShiftManager (SM)keycabinet.
Distractors: B This answer isplausible since itisa keylocation, but it doesnothold the referenced keys.
the referenced keys.
D This answer isplausible since itisa keylocation, but id toesnothold thereferenced keys.
Page: 184of214 16March 2020
2020NRCROExamrev0 Test ID: 330066 QuestionE66 lofo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: 0.00 S stem ID: 2131121 User-Defined ID:
Cross Reference Number:
Topic:
. 1d. In accordance with the Conduct ofOperations Manual, describe the reuirements for followin the NumField 1:
NumField 2:
Text Field:
Page: 185of214 16March 2020
j 2020NRCROExamrev0 Test ID: 330066 Comments: Ed#Ajf1M*TagiRl(((lQW(f(6 None None FT None WWFFF/JiiaeRAkarMineMWiWWE None
///':/: .'.
. :::.-'/.
.:..'.. . .::: ::::::-- //
/-:
/ ':"'.
- /'2 Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(10)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): OP-PB-108-101-1006, RT-O-100-960-2 Learning PLOT DBIG-1529, 1d -
Ob'ective:
K/ASystem:G2.1.8 Ability to Importance:
coordinate personnel RO /SRO activities outside the 3.4/4.1 control room.
K/A NA Statement:
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 186of214 16March 2020
=
20:20 NRCROExamrev0 Test ID: 330066
$A$pjjff3k)j$W(ff(f$fQff[%)y%&AjjffMJJiffWIffffff(fffffff)$jjjQ$[fff$fdf#g$4$$f IAWHU-AA-104-101, Procedure UseandAdherence, which ofthe following lists conditions that allow taking deliberate action that departs from procedural guidance during anemergency, whennoother course ofaction isimmediately apparent?
Action(s) taken to....
- 1. protect thehealth andsafetyof the public
- 2. prevent damage toplant safeguards equipment
- 3. maintain grid stability during anEmergency Generation condition A. 1ONLY B. 1and2 ONLY C. 1and3ONLY D. 1,2,and3 Answer: A AnswerExplanation . .. .. CA 1... .., . . ......... .
Justification: Choice Basis orJustification Correct: A Thereference procedure provides the following: The licensee may take reasonable action that departs from alicense condition ora Technical Specification inanemergency when:
1.Theaction isimmediately needed toprotect thepublic health and safety. Answer A is correct.
Distractors: ......B Plausible since there aremanyprograms designed tomaintain the healthofsafety andsafeguards systems (logging ofTSsystems, protected systems, etc).
C Plausible since grid stability isimportant tothepublic, butthis is controlled bythe TSOwhowould give Peach Bottom direction.
D Plausible since there aremanyprograms designed tomaintain the healthofsafety andsafeguards systems (logging ofTSsystems, protected systems, etc).
Plausible since grid stability isimportant tothe public,but this is controlled b the TSOwhowouldive Peach Bottom direction.
Page:187of214 16March 2020
2020NRCROExamrev0 Test ID: 330066
-Question 6Tinfor Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 2 Difficul : 1.00 ..
S stem ID: 994571 User-Defined ID: ILT-1529-1A-002 Cross Reference Number: 2.1.1 To ic: ILT-1529 De artin fromrocedure duetoanemerenc NumField 1: 4721 NumField 2: N/A Text Field: B Comments:
E'[TTfffffffff'UTTMAAif2fjj None
"##f',"TT',"Tff[LGL'fT"""""f////fjfifff(4 None
[Effiff(fNTL,"E[','T(fjfjji None TW///AE None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(10)
Source Documentation Source: New ModifiILT Other Previo ed Bank Bank us2 X NRC Exams Reference(s): HU-AA-104-101 Learning PLOT DBIG-1529, 1a Ob'ective:
K/ASystem:G2.1.1 Knowledge of Importance:
conduct ofoperations RO/SRO reuirements. 3.8/4.2 K/A NA Statement:
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 188of214 16March2020
2020NRCROExamrev0 TestID: 330066
$$Eij&jMigkW igif$f$kkg,$k "Wiffffff)$WijA$fff$% V""Tff$ifif$%fgy&$fQ$giffili$giMMA Which ofthe following conditions isaviolation ofa Unit 2 Safety Limit?
A. Reactor Coolant pressure reaches 1400 psig during a hydro.
B. RPVleveldrops to-165 inches during anATWS.
C. Reactor poweris 17% at650psig reactor pressure during anATWS.
D. MCPRis1.22 at100% power and1034 psig Reactor pressure.
Answer: A Answer Explanation; Choice BasisorJustification Correct: A Allofthe choices are safety limitswith values below the safetylimit violation exceptfor choice "A". TheSafety Limit isreactorsteam domepressure shall be51340 psig.With apressure of1400 psig the safety limit for RPVpressure is violated.
Since allofthe choices areactual parameters that challengethe safety limitsallofthe distractorsare plausible.
Distractors: B This answer isplausible. TheRPVlevel safety limit is;Reactor vessel waterlevel shall begreater than top of active fuel. The value of-165 inches hasnot exceeded this limit (-172 inches).
ThusnoSLviolation.
C This answer isplausible. ThelowRPVpressureor low flowsafety limit requiresthatReactor power bebelow 22.6% when RPV dome pressure isless than 700psia orcore flow isless that10% or rated. With RPVpressure lessthan 700psia, power must be less than 22.6%, andthe thisanswer haspower at17%. ThusnoSL violation.
D This answer isplausible. Thehigh RPVpressure andcore flow safety limitrequires MCPRbe2 1.15. Conditions aregiven for high flowandnormal RPVpressure andtheMCPRvalue isabove thelimit asreuired. ThusnoSLviolation.
Page:189of214 16March 2020
/;
2020NRCROExamrev0 Test ID: 330066
'Questionh68 Info ... AC A . .
Tyn Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoCom lete: 0 Difficult: 1.00 S stemID: 1140387 User-Defined ID:
Cross Reference Number: G2.2.22 To ic: ILT 1800-8-006 NumField 1:
NumField 2:
Text Field:
Comments:
[j[F'WRfff(fff) None FET'E',['$(([Tffffffffff/2 None j[$ff(Mf ffff*['*(CE((['f['Tffffj@ None TMffffff(d None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(5)
Source Documentation Source: New ModifiILT Other Previo ed Bank Bank us2 X NRC Exams Reference(s): Unit 2 TechS ecSafe Limits Learning PLOT 1800, -
8 Ob'ective:
K/ASystem:G2.2.22 Knowledge of Importance:
limiting conditions for RO/SRO operations andsafety 4.0/4.7 limits.
K/A NA Statement:
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 190of214 16March 2020
2020NRCROExamrev0 TestID: 330066 j$gW"%N$f)Affpfiffggf #WffffffffffjfM$ggff$$ggg3*RfffffjffffjjQ%g ;ff5f$f4g(gggM35 Unit 2isatfullpower when anATWS occurs:
a T-246-2, "Maximizing CRDFlow ToTheReactor Vessel" isbeingperformed e All CRDhydraulic components areina normal lineup.
Inorder tomaximize flow inaccordance with T-246-2 thefollowing would valves position?
beinwhat DriveWitPreas CRD11owControl M0-2-03.-02D AO-2-3-019A A. Closed Closed B. Open Closed C. Closed Open D. Open Open Answer: D Page:191of214 16March 2020
i 2020NRCROExamrevo Test ID: 330066
<<<<<<Justification: Basis orJustification Choice Correct: D T-246-2 is'used tomaximize CRDcooling water underneath theCRD blade toinsert control rods. CRDprovides HCUcharging, controlrod drive water, andCRDblade cooling water. PertheP&ID, HCU charging taps off before (upstream) ofboth the CRDFCVandthe drivewater valve. Drive water water taps off afterthe CRDFCVand before the drive water valve. CRDblade cooling taps off after (downstream) ofboth the CRDFCVandthe drive water valve. Thus, both valves must beopened. Theprocedure requires that theDrive Water valve and CRDFlow valve both beopened.
Distractors: A CRDprovides HCUcharging, control rod drive water, andCRDblade cooling water. Perthe P&lD, HCUcharging taps off before (upstream) ofboth theCRD FCV andthe drive water valve. Drive water tapsoff after the CRDFCV and before the drive water valve. CRDblade cooling taps off after (downstream) of both the CRDFCVandthedrive water valve. Misinterpretation oftheP&IDmakes this answer plausible.
B CRDprovides HCUcharging, control rod drive water, andCRDblade cooling water. PertheP&lD, HCU charging taps off before (upstream) ofboth the CRDFCVandthedrive water valve. Drive water tapsoff after the CRDFCVandbefore the drive watervalve. CRDblade cooling taps off after (downstream) of both the CRDFCVandthedrive water valve. Misinterpretation ofthe P&lD makes this answer plausible.
C CRDprovides HCUcharging, control rod drive water, andCRDblade cooling water. Perthe P&ID, HCUcharging taps off before (upstream) ofboth the CRDFCVandthe drive water valve. Drive water taps off after the CRDFCVandbefore the drive water valve. CRD blade cooling taps off after (downstream) ofboth the CRDFCV and the drive water valve. Misinterpretation oftheP&IDmakes this answer lausible.
Page: 192of214 16March 2020
2020NRCROExamrevo TestID: 330066 Question 69Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stem ID: 2130729 User-Defined ID: PBIG-2101-6 Cross Reference Number: 2.2.2 Topic: PBIG-2101-6 Statethe for bases each RPV ofT-101, step Control G2.4.18 NumField 1:
NumField 2:
Text Field:
Page:193of214 16March 2020
2020NRCROExamrevo Test 330066 ID:
Comments: !Pf4Rf//ffd1GW(asf(iiBW(fditW';W(MI None v
None None Ps chometrics Level of RO Knowledg e
High 10CFR55.41(b)(6)
SourceDocumentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): T-246-2, M-356 Learning PLOT PBIG-2101, -
6 Ob'ective:
K/ASystem:G2.2.2 Abilityto Importance:
manipulate theconsole RO/SRO controls asrequired to 4.6/4.1 operate the facility between shutdown and desi natedower levels.
K/A NA Statement:
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 194of214 16March2020
A 2020NRCROExamrev0 Test ID:330066 AAgr/AAF/4#&%?^%i&$rArktWffffNJ21ASAPAfif)/AibhifffffffA5titWT/Af ftatoirgef#aW Theplant isresponding toconditions requiring venting the CRDwithdraw lines "Control IAWT-215-2, Rod Insertion byWithdraw Line Venting".
a SROhasdeclared this activity as"saving plant equipment" Which ofthe following iscorrect when performing this activity?
A. There isnoneedto notify Radiation Protection astheactivity isbeing performed in response toanemergency.
B. There isnoneed tonotifyRadiation Protection since theactivity iscovered onworker common RWPs.
C. Radiation Protection mustcreate a new RWP prior ofwork.
tothestart D. Radiation Protection shall benotified tomonitor thework.There isnoneedtocreate a
newRWPprior tothe start ofwork.
Answer: D Page: 195of214 16March 2020
2020NRCROExamrevo Test ID: 330066 Justification: Choice Basis orJustification Correct: D Thevent activity inthe question takes place onacatwalk above the HCUsandthis isgreater than 7feet from the floor.
Thecatwalk isnot a commonly traveled area andisnot commonly surveyed byradiation protection andnormal RWPs donot allow toentry into these types ofareas. Toaccess this area, somesort ofradiation protection actions isrequired.
RP-AA-403 provides the following: :When immediate action is required tosave personnel orplant equipment ortorespond to plant security events, then entry toanarea without anRWP may be PERMITTED." It also says "If authorization isgiven fo the entry without anRWP,then PROVIDE RPcoverage, as required, to meet the objectives oftheRWPprogram." When the job/situation iscompleted, then DOCUMENT the performanceof the job/situation through the corrective action process andENSURE accounting ofdose equivalent received during the unplanned activities.
Notifying RPisrequiredto monitor, andnonewRWPis required.
Distractors: A Plausible asduring anemergency some actions are expedited, however Radiation Protectin isasafety issue and isnot bypassed.
B Plausible asthefloor elevation area is covered bythe common RWP,andentry into non-contaminated areas is allowed bytheir common RWP,however performance of parts oftheactivity are atelevations above 7 feet and are not covered under the common RWP.
C Plausible asparts ofthe activity arenotcovered under the common RWP,however, there isnorequirement fora new approved RWPfor this "saving plant equipment" activity.
Page: 196of214 16March 2020
2020NRCROExamrev0 Test ID:330066 L
Questionif0!ijnfo .. . .
Question T e: Multi leChoice Status: Active Alwa sselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficul : 0.00 S stem ID: 2130206 User-Defined ID: ILT-1760-4-5 Cross Reference Number: 2.3.7 Topic: ILT-1760-4-5 RWPrequirements Discuss underemergency conditions.
NumField 1:
NumField 2:
Text Field:
Page: 197of214 16March 2020
=s~
2020NRCROExamrev0 Test ID: 330066 Comments: 55ffiB2$?MT4i$(((@f(gB None T
K
[##
Pschometrics Level of RO Knowled e Memory 10CFR55.41(b)(12)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): T-215-2, RP-AA-108,RP-AA-403 Learning PLOT 1760-4 -
Ob'ective:
K/ASystem:G2.3.7 Ability tocomply Importance:
with radiation workpermitRO / SRO requirements during 3.5/3.6 normal orabnormal conditions.
K/A NA Statement:
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 198of214 16March 2020
i 2020NRCROExamrev0 Test ID: 330066 Youhave been tasked withperforming anaction IAWanOperational Transient procedure.
(OT) e Thegeneral area radiation level inthe area ofthetask is1003mr/hr.
= TheShift Manager has NOTdeclared anemergency IAWRP-AA-460-003, "Access To HRAS/LHRAS AndContaminated Areas ToA Potential InResponse Or Actual Emergency".
which ofthe following states ALLtheradiological requirements for into entry task the area?
A. There areNOadditional radiological requirements other those than associated with your normal RWP.
B. Task/area specific RWP,and High radiation areabrief prior toentry. ONLY C. Task/area specific RWP, High radiation areabrief prior toentry, and Issuance ofaLHRAkeyONLY D. Task/area specific RWP, High radiation areabrief prior toentry, issuance ofaLHRAkey, and RPcoverage ofyour entry.
Answer: D Page: 199of214 16March 2020
j 2020NRCROExamrev0 Test lD:330066 Justification: Choice Basis orJustification Correct: D IAWNISP-RP-013, anaccessible areawithdoserates greater than 100mr/hr at30cm requires asa high posting radiological area (HRA), andanarea greaterthan 1000 mr/hr requires posting asalocked high area radiological (LHRA),
along with other barriers (locked gate,etc).
Inthequestion stem, the dose rates inthe task areaare 1003 which mr/hr, makesthe task area a LHRA.IAWRP-AA-460-003, entryinto thearea under the given circumstances, anHRA requires brief, a key, andescort byRPpersonnel. LHRA'sarealsonot covered under the normal RWPandatask/area specific one would beissued.
Distractors:A Thisdistractor isplausible it fhestudent RP mis-applies guidance. The majority of tasks for intheplant everyday activities only require the normal RWPconditionsbemet.
B This distractoris plausible if the student RP mis-applies guidance. Themajority oftasks for intheplant everyday activities donotrequire RP assistance. Forinstance, entry into a posted HRAonly requires a brief,.but noRPcoverage.
C This distractorisplausible if the student mis-appliesRP guidance. There arerad areas where akey anda brief areall that isrequired, however a locked hirad areawouldrequire a
brief, a ke andRPescort.
Page:200of214 16March 2020
d 2020NRCROExamrev0 Test ID:
330066
~Question 71Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult : 0.00 S stem ID: 2130748 User-Defined ID: PLOT-1770-3 Cross Reference Number: 2.3.13 Topic.
3.Given aworksituation andaccompanying radiological information, evaluate the A todetermine
'ob NumField 1:
NumField 2:
Text Field:
Page: 201of214 16March 2020
=e,--
l 2020NRCROExamrev0 TestID: 330066 Comments: F/f5/A3P' Ai$($RW((((if
"*t None None k////'/
F None None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(12)
Source Documentation Source: New Modifi ILT Other Previo X ed Bank Bank us2 NRC Exams Reference(s): NISP-RP-013, RP-AA-460, RP-AA-460-003 Learning PLOT 1770, -
3 Ob'ective:
K/ASystem:G2.3.13 Knowledge of Importance:
radiological safety RO / SRO procedures pertaining to 3.4/3.8 licensed operator duties, such asresponse to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access tolocked high-radiation areas, alininfilters, etc.
K/A NA Statement:
REQUIRED None MATERIALS:
Notesand None Comments:
Page:202of214 16March2020
see 3e, f!:::
S l; 2020NRCROExamrev0 Test ID: 330066
$fAfi 7$Wf!fff%WARiWW//fiF&MMSMidW/aifMiAWTTAkith InT-103"Secondary Containment Control", ALARMandACTION level thresholds (forradiation, water andtemperature) are established todetermine levels, the applicable steps tobetaken tomitigate or terminate the event. Which of thebelow statements is the basis for establishing the "ACTION" Levels for theT-103 controlparameters?
IAWthe T-103 Bases, the ACTION levels arethe..,
A. maximum limits that the Secondary Containment canstructurally withstand bydesign.
B. minimum limits which must be exceeded before entry into T-103 iswarranted.
C. minimum values used toalertthe operator toa potential radioactive release.
D. maximum safe operating limits above which damagemayresult toequipment required for safe shutdown.
Answer: D Answer Explanation
'. CAAA AC in .
TEE1 xn . .. . .
Justification: Choice Basis orJustification the Correct: D T-103 Bases, Secondary Containment Control f3asesJrovides following: "The Action Levels contained inTables SC/R-1, SC/L-2 and SC/T-3 correspond tothe Maximum Safe Operating values (MSO) for the respective Secondary Containment parameters.The MSO is the value atwhich neither equipment necessary for thesafe plant shutdown willfail norpersonnel access necessary for thesafe plant shutdown willbeprecluded."
Distractors: A This distractor isplausible since exceeding theaction levels in2 areas requires anemergency blowdown, which represents adrastic thermodynamic stress ontheRPVitself.
B Several T-103 entries arewhenthe ALERTlevels arereached (and notthe Action levels). TheAlert levels areless than theAction levels.
Thedistractor isplausible if thestudent misinterprets theprocedure ent requirements.
C Onepurpose ofthe T-103 procedure istolimit radioactivity release from theSecondary Containment. High temperatures, high radiation levels, high water levels, etc.canbeall related toa primary system discharging intothesecondary containment. This makesthis distractor lausible.
Page: 203of214 16March 2020
ys::=:= : +:x m=: a =-
CI'.- ..-
2020NRCROExamrev0 Test ID: 330066 C
Question12:Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoCom lete: 2 Difficult: ..
1.00 S stemID: 993740 User-Defined ID: ILT-2103-6-001 Cross Reference Number: 2.4.18 To ic: ILT-2103-6-001 Basis for establishinAction Levels NumField 1: 3161 NumField 2: N/A Text Field: B Comments:
PM)jifjT/fffj None UMCLTEDTfff/ffjffffff/A None FEfjE'FXi"f'***ETTT'fffff) None bMJf fffffff[([f?ffiffff$ None Ps chometrics Level of RO Knowled e Memory 10CFR55.41(b)(10)
Source Documentation Source: New ModifiILT Other Previo ed Bank Bank us2 X NRC Exams Reference(s): T-103, T-103 Bases Learning PLOT PBIG-2103, -
6 Ob'ective:
K/ASystem:G2.4.18 Knowledge ofthe Importance:
specific bases forEOPs. RO/SRO 3.3/4.0 K/A NA Statement:
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 204of214 16March2020
=1:: = :';>;.>
@W@j b !
2020NRCROExamrev0 Test ID: 330066 4$ffff)$WfW/fldifffh$fffj/fMf /M ///F/AEt%%M6WAs1JJ Unit 2is100%power a A fire isreported in Unit 2 Circulating Water Pumproom FireBrigade isdispatched along with theFloor Supervisor Theperson responsible for deciding a strategy toextinguish thefire -(1)-
isthe AND IAWON-114 "Actual Fire Reported.", ifthe fire cannot beextinguished andOff-site assistance is required thecontrol roomwill perform a-(2)- on the affectedUnit A. 1)Incident Commander
- 2) GP-3-2(3) "Normal Plant Shutdown" B. 1)incident Commander
- 2) GP-4 "Manual Reactor Scram" C. 1)Floor Supervisor 2)GP-3-2(3) "Normal Plant Shutdown" D. 1)Floor Supervisor 2)GP-4"Manual Reactor Scram" Answer: A Page:205of214 16March 2020
n ;
at!;
2020NRCROExamrevo Test ID: 330066 Justification: Choice Basis orJustification Correct: A inaccordance with FF-0Hhe incident commanderb responsiblefor deciding onthe strategy toextinguish the fire. Inaccordance with ON-114 itfhe firecannot beextinguished andoff-site assitance is requiredthe control roomwill commence a GP-3normal plant shutdown for the affected unit.
Distractors:B First part iscorrect Plausible asa fire requiring off-siteassistance would bea largefire and a GP-4 might beneccesary atsometime asmore systems are affected bythe fire, however ON-114 does not mandate a GP-4 is performed ontheaffected unitandonly says tocommence a GP-3 shutdown.
C Plausible as the Floor Supervisor would respond tothe command post andbeing in asupervisory role the candidate maymistinterpret their duties during the fire.Thefloor supervisor would actasa technical liaison between thecontrol roomandtheIncident Commander, the firefighting decisions areleft tothe Incident Commander.
Second partiscorrect Plausible astheFloor Supervisor would respond tothe command post andbeing inasupervisoryrole the candidate maymistinterpret their duties during the fire. Thefloor supervisor would actasa technical liaison between thecontrol room and the Incident Commander, the firefighting decisions are left totheIncident Commander.
Plausible asafire requiring off-siteassistance would bea large fire andaGP-4might beneccesary atsometime asmore systems are affected bythe fire,however ON-114 does not mandate a GP-4is performed ontheaffected unitandonly says tocommence a GP-3 shutdown.
Page: 206of214 16March2020
i F 2020 NRCROExamrev0 Test ID: 330066 Question 73info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficul : 0.00 S stem ID: 2131771 User-Defined ID:
Cross Reference Number: 2.4.35 Topic: 29.In accordance with FF-01 describe for therequirements reuinn off siteassistence NumField 1:
NumField 2:
Text Field:
Page:207of214 16March 2020
2020NRCROExamrev0 TestID:330066 Comments:
/
Pschometrics Levelof Diffic Time RO Knowledge ulty Allowance minutes Memory 10CFR55.41(b)(10)
Source Documentation Source: X New Exam item Previous NRC Exam Modified Bank Other ExamBank ILTExam Bank Reference s: FF-01 andON-114 Learning PLOT 157029 - -
Ob'ective:
K/ASystem: 2.4.35 Knowledge of Importance:
local auxiliary operator RO /SRO tasks during an 3.8/ 4.0 emergency andthe resultant operational effects K/AStatement:
REQUIRED NONE MATERIALS:
Notesand This question meets theK/Aasthe Comments: incident commander isa local auxiliary operator andthe decisions they makein that role could cause thecontrol roomto shutdown thelant.
208of214 Page: 16March 2020
2020 NRCROExamrev0 Test ID: 330066
$40%$%f%PkW/$&bWfffhfffMWbdfflfTf%Wf8%MART$9WJ$5 Unit 2isat100%power with the following:
a Aninspectionmust be performed ona 120 VACelectrical panel.
- The120VACelectrical panel provides indication tosomecontrol roomswitches. These room control doNOTprovide a zone OfProtection.
switches a TheElectricians performing the inspection need tobeable toopen thepanel'sdisconnect switchfor personnel protectionduring some portions of the inspection.
- TheElectricians performing theinspection also needtobeable toclosethepanel's disconnect switch forperiodic This verifications. willcause the control roomswitch tolight indications up.
- It for isdesired the Tagout tobecontinuously hung during the sorepeated activity, and tagclearing isNOTrequired.
re-hanging Whichoneofthefollowing describes the taggingarrangement needed tosupport the requested maintenance activity inaccordance with OP-AA-109-101, "Personnel andEquipment Tagout Process" with tothe regards control roomswitches?
Roomswitches TagtheControl with...
A. Danger Tags ONLY.
B. information/Caution Tags ONLY.
C. Special Condition TagsONLY.
D. Danger Tags andinformation Tags simultaneously.
Answer: B E L AL Basis E L AnswerExplanation .
Choice orJustification Correct: B Inaccordance with OP-AA-109-101 section7.4.1.3WhenMain Control Board switches are tagged toindicatetagoutconditions, then apply anInformation/Caution Tag Distracters: A Plausible ascontrol roomswitches canbeused asenergy isolation points forzone ofprotection, however thecontrolroomswitch indications are theonly thing affected andthey arenotisolation points asthey receive power anddonotprovide a connectionfor power.
C Plausible asSpecial Condition Tags would beusedfor electrical the panels disconnect switch which actsaspersonnel protection but allows thetagged component tobemanipulated. Thecandidate might misapply this knowledge tothechanging light indications and believe aSpecial Condition Tagisalso requiredforthe Room Control switches D Plausible asDanger andInformation Tagscanbehung together, however there isnorequirement tohang a Danger tagontheControl Roomswitch asthe switch isnot providing personnel protection.
Page: 209of214 16March 2020
2020NRCROExamrev0 TestID:330066 Question 74info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2130210 User-Defined ID:
Cross Reference Number: 2.2.13 . . ..
To ic: SCT-2 NumField 1:
NumField 2:
Text Field:
210of214 Page: 16March 2020
= .:'..;.,,,,
2020NRCROExamrev0 TestID: 330066 Comments:
None
,f None
/iijii" ji" Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(10)
Source Documentation Source: New Modifi ILT OtherPrevio ed Bank Bank us2 X NRC (16496 Exams 21)
Reference(s): OP-AA-109-101 Learning ILT Clearance andTagging -
Clearance Objective: Writer/Preparer -
Describe Clearance Tag Standards related toClearance andTagging rocess K/ASystem:G2.2.13 Knowledge of Importance:
tagging andclearance RO/SRO rocedures. 4.1/4.3 K/A NA Statement:
REQUIRED None MATERIALS:
Notes and None Comments:
211of214 Page: 16March2020
Jt
/'.
/////////a/Nara Unit 2 isoperatingat100% power withthefollowing:
a Aninspection mustbeperformed ona 120VACelectrical panel.
e The Electricians performing theinspection need tobeable toopen thepanel's disconnect switch for personnel protection duringsomeportions oftheinspection.
a The Electricians performing theinspection also need tobeable toclose thepanel's disconnect switch for periodicverifications.
a It isdesired forthe Tagout tobecontinuously hung duringthe activity, sorepeated tag clearing andre-hanging isNOTrequired.
Which oneofthe followingdescribes the tagging arrangement needed tosupport therequested maintenance activity inaccordance withOP-MA-109-101, Clearance andTagging?
Tagtheelectrical panel's disconnectswitch with.
A. a Danger Tagonly.
B. anInformation Tagonly.
C. aSpecial Condition Tagonly.
D. both a Danger Taganda Special Condition Tag simultaneously.
Answer: C fWWff##d#Wf#d//fdflf#d2//3Wfd/dd3 Choice BasisorJustification Correct: C A Special Condition Taghasequal authorityto a Danger Tagto provide personnel protection,but also allows the tagged component tobemanipulated without clearing thetag, asrequired bythis maintenance activity.
Distracters: A A Danger Tagwould notallow re-positioning the disconnect switch withoutclearing thetag. Plausible because theDanger Tag does provide the personnel protection required.
B An Information Tagdoesnotprovide therequired personnel protection. Plausiblebecause theInformation Tagwould allow re-positioning thedisconnect switch without clearing thetag.
D A Danger TagandSpecial Condition Tagarenotallowed tobe placed onthe samecomponent atthesame time. Plausible because theDanger Tagdoesprovide thepersonnel protection required and theSpecial Condition Tagisused toallow manipulation ofa tagged com onent.
PB-OPS-EXAM-ILT-2015 Page:1 of2 12March 2020 CurrentView
[D@@%f$3@@@d!%$@@$@d Question T e: Multi leChoice Status: Active Alwasselect ontest? No Authorized forractice? No Points: 1.00 Time to Comlete: 0 Difficult : 0.00za
,,,zwwwam mean:= =ammu =a .. Tf :: /
.>&"WL'i. .
- gi'T
S stemID: 1649621 User-Defined ID:
Cross Reference Number: 2.2.17 mowuw,,zma3r:mm=mawongmum msmos:manm:swmar--
To ic: SCT NumField 1:
NumField 2: A NRC Text Field:
Comments: Psychometrics Level of Difficulty TimeAllowance RO Knowledge (minutes)
MEMORY 10CFR55.41(b)
(10)
SourceDocumentation Source: New Examitem X Previous NRCExam (2017)
Modified Bank Other Exam Bank X ILT ExamBank (2114939)
Reference(s): OP-MA-109-101 Learning O2.0-007 Objective:
K/A System: importance; RO 2.6 K/A 2.2.17 -
Knowledge ofthe process for managing Statement:maintenance during activities power operations, such asrisk assessments,work prioritization, and coordination with thetransmission system operator.
REQUIREDNONE MATERIALS:
Notes and Comments:
Associated objective(s):
DESCRIBE the Clearance TagStandards related tothe Clearance andTagging process.
PB-OPS-EXAM-ILT-2015 Page: 2 of2 12March 2020 Current View
. = =
2020 NRCROExamrevo Test ID:330066 gWQfgggjjggWff/fggir$gfffffjfff ff(MyMj ffgffjjgff(fffjjggfgy$fffffgfggpgg Unit2isat100%power. Youare directed toperform atask intheplant.
= Your annual cumulative TEDE is 1600 mrem
- Youare performing work in the RCAunder anRWPwith thefollowing setpoints
- Dose: 400mrem
= Doserate: 1000 mrem/hr Whilestill performing workintheRCA you look atyour EDandseethe following::
= 325mrem IAWRP-AA-1008, "Unescorted Access ToAnd Conduct InRadiologically Controlled what Areas", action isrequired,if any?
A. Nospecific action isrequired since your RWP doselimit hasNOTbeen exceeded.
B. Youmust exit the RCAsince 80%ofyour RWP dose limit hasbeen exceeded.
C. Youmustexit the RCAsince your annual accumulated doselimit hasbeen exceeded.
D. Youmuststop work, travel toa low dose waiting area,and callRP since80%ofthe RWPdoselimit hasbeen exceeded.
Answer: B Answer:Explanationn . n . ..... n . . .... xx.... . x Justification: Choice Basis orJustification Correct: B Thenormal operations RWPdose limit is400mrem. IAW RP-AA-1008, if80%ofthe dose limit isreached, RCAexit is then required. IAWRP-AA-203, theadministrative dosecontrol levels have been established for Total Effective DoseEquivalent (TEDE) as2000 mrem/year. Thus, theRWP80%doselimit hasbeenexceeded, whereas the administrative doselimit hasnotbeenexceeded.
Distractors: A This answer isplausible if thecandidate misinterprets theRWPdoes limitormakes acalculational error, since the80%dose of320 limit mremisclose tothedosereceived of325mrem.
C This answer isplausible if thecandidate misinterprets the administrative dose limit ormakes a calculational since error, the 2000 dose limitisclose tothe accumulated dose of325+ 1600 = 1925 mrem.
D This answer isplausible since the operator leaves thehighdose area andwaits inalowdose area. Butleaving theRCAisrequired.
Page: 212of214 16March 2020
2020NRCROExamrev0 TestID:330066 Question 751nfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: 0.00 S stemID: 2130810 User-Defined ID:
Cross Reference Number: 2.3.15 Topic: 4.State theadministrative exposure limits inaccordance with RPAA 203.
NumField 1:
NumField 2:
Text Field:
213of214 Page: 16March 2020
= n,, m n , ....
2020NRCROExamrev0 TestID: 330066 Comments: WF####T'Tg"'"' "N"T#"''tNone
'C"*"f"'P"Tf"'M This question meets theK/A because thecandidate must usetheir knowledge ofwhat information isbeing provided bytheir personnelmonitoring device dosimetry)
(electronic andusing that knowledge along withRadprocedures reconize limitations onwork.
None None Ps chometrics Level of RO Knowled e High 10CFR55.41(b)(12)
Source Documentation Source: New Modifi ILT OtherPrevio X ed Bank Bank us2 NRC Exams Reference(s): RP-AA-203, RP-AA-1008 Learning PLOT 1730, -
4 Ob'ective:
K/ASystem:G2.3.15 Knowledge of Importance:
radiation monitoring RO/SRO systems, such asfixed 2.9/3.1 radiation monitors and alarms, portablesurvey instruments, personnel monitorin e uiment, etc.
K/A NA Statement:
REQUIRED None MATERIALS:
Notesand None Comments:
214of214 Page: 16March 2020
2020NRCSROExamrev0 Test ID:332227 E$PAWff)7ffiEff//fAffff//////AFFANJ582WASAW#2W7//JATAff#//7EBF//A T-116, "RPVFlooding" Sheet 1(non-ATWS)wasentered duetoatransient inUnit 2.
Thefollowing conditions exist:
= tolosing Prior level indications the Shift Technical calculated Advisor a leak from rate theRPVof approximately15,000 gpm a Only the'D'RHRpumpisinjecting into theRPV
= RPVpressure iscurrently 90psig and down slowly e SRVsindicate Four open
= OpenSRVtailpipe temperatures are slowly 335degrees F and rising Torus levelis14.5 feet andlowering slowly conditions, Forthese (1) what isthestatus oftheMain what SteamLines and(2) isrequired?
action TheMainSteam Lines are (1) Therequired
. actionisto (2) .
A. (1) flooded (2) close MSIVs andMSLdrain valves B. (1) flooded (2) pursue alternatedepressurization C. (1) NOTflooded (2) continue with injecting RHR;DONOTaddadditional
'D' injection sources D. (1) NOTflooded (2) continue injecting with RHR;addadditional
'D' sources injection Answer: D Page: 1of77 16March 2020
o
- m = = = -
2020NRCSROExamrevo Test ID: 332227 Choice Basis orJustification Correct: D PerT-116 Sheet 1 Note 41,acombination ofindications mustbeused to determine if the main steam lines areflooded. Inthis case,there isonly one indication that the main steam lines maybeflooded (SRV open). Allother indications indicate the main steam lines arenot flooded(tail pipes arenot subcooled, Torus level isstill dropping). Since the Main steam lines arenot flooded T-116bases says that tofilltheRPV,theinjection rate mustatleast begreater than the rate ofinventory losses from anysystem leaks or breaks. Since the leak rate wascalculated at15,000 gpm, oneRHRpump isnot enou hto fillthe RPV.Additional in'ection sources would beused.
Distractor A Plausible ifthe candidate fails torecognize that the main steam linesarenot s: flooded based on their evaluation of the conditions.
Plausible because ifflooded to the main steam lines oneofthe actionsisto close the MSIVs and MSL drains.
B Plausible ifthe candidate fails torecognize that themain steam linesarenot flooded based ontheir evaluation ofthe conditions.
T-116 hasdirection tousealternate depressurization atleast if 2 SRVsare not open. Plausible ifthe candidate does not recall thenumber ofSRVs needed before using alternate depressurization .
C First part iscorrect.
Plausible since theRPVisnot flooded tothe steam lines andT-116 bases state injectionneed not beimmediately maximized asunnecessarily rapid flooding willonly increase the possibility ofequipment damage. The candidate maymisapply this step andnotprovide enough water for flooding.
Page: 2 of77 16March 2020
- m 2020NRCSROExamrev0 Test ID
- 332227 tinfo WA Question Question T e
- Multi leChoice Status: Active Alwasselect on test? No Authorized forractice? No Points: 1.00 Time toComlete: 0 Difficult: 1.00 S stemID: 1140449 User-Defined ID:
Cross Reference Number: 295006 A2.03 To ic: ILT2116-5-001-SRO NumField 1:
NumField 2:
Text Field:
Comments: Ps chometrics Level of Difficult Time RO Knowledge y Allowance minutes HIGH 10CRF55.43 b5 Source Documentation Source: NewExamitem Previous2 NRC Exam Modified Bank Other ExamBank X ILT ExamBank (2114437)
Reference(s): T-116 Learning PLOT-1560-11 Ob'ective:
K/ASystem: 295006SCRAM -
importance:
RO/SRO 3.8/ 4.3 K/AStatement: A2.03Ability todetermine and/or interpret thefollowing asthey applytoSCRAM:
Reactor water level REQUIRED None MATERIALS:
Notes and This question meets theK/Aand Comments: 10CFR55.43 criteria anSROquestion for because the candidate mustdetermine Reactor water levelwhenafull SCRAM hasoccurred andwithout level indication by interpreting thedata giveninthe stem.
Theymustthen makea determination on the next steto erform.
Page: 3 of77 16March 2020
l s 2020NRCSROExamrev0 TestID: 332227 4!'TdBE%ddWNf%@WfdhAff#hi3R$fWW)Wf%r4df$Wd#WA$19ffhif@
Unit 2isoperating at 100% power with the following:
Annunciator 217 F-5, REACT BLDG COOLING WATERSUPPLY LOPRESS, alarms.
RBCCW pressureis 65 psigandfluctuating.
The"A" RBCCW pump isoperating.
a The"B" RBCCW pumpCANNOT bestarted.
Annunciator 217E-5, REACT BLDG COOLING WATER SUPPLY HITEMP,alarms.
a RBCCW supply temperature is 1200F and rising slowly.
a There isNOevidence ofsystem leakage.
Anoperator inthe field reports that the "A"RBCCW pump sounds like it isexperiencing severe cavitation.
e Venting the RBCCW pumphashadnoeffect onthe cavitation.
Which oneofthe following describes therequired control of the plant inaccordance with ON-113"Lossof RBCCW" RBCCW if system continues todegrade?
A. NOReactor power reduction orsecuring ofequipment isrequired.
B. Shutdown therunning RWCUpump(s) andlowerReactor powerperGP-9-2, Fast Reactor Power Reduction.
C. Lower Reactor power per GP-9-2, Fast Reactor Power Reduction, andtrip oneRecirc pump.
D. Scram theReactor per GP-4, Manual Reactor Scram, andtrip both Recirc pumps.
Answer: B Page: 4 of77 16March 2020
2020 NRCSROExamrevo Test ID: 332227 Choice Basis orJustification Correct: B ARC217F-5 requires entry into ON-113 based onlowRBCCW pressure andfailure ofstandby pumptorestore pressure.
Since the standby pumpisunavailable, the running pumpisoperating abnormally, andsystem temperature ishigh anddegrading, restoration ofRBCCW isnotimminent. Therefore, ON-113 step2.2 requires shutting downthe running RWCUpumps andlowering Reactor power per GP-9-2.
Distracters: A Since conditions show degradation ofRBCCW andrestoration isnot imminent, ON-113 requires securing RWCUpumps andlowering power. Plausible because ifconditions were given thatsystem pressurerestoration wasimminent, then nosecuring ofequipmentor power reduction would berequired.
C Noindicationsare given for degraded Recirc pumptemperatures, therefore tripping of a Recirc pump isnotrequired. Plausible because tripping ofRWCU pumps is required toreduce heat load andtripping oneRecirc pump ispossibleandwould alsoreduceheat load. Also plausible because ifaRecircpumpexperienced a high temperature, then tripping of the pump would become necessaryper ON-113.
D Scramming the Reactor isnot required. Plausible becauseON-113 step 2.6 provides this exact direction if itbecomes necessary to shutdown both Recirc pumps duetohigh temperatures.
Page: 5 of77 16March2020
n n .
i 2020NRCSROExamrev0 Test ID: 332227
.Question 2info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized forractice? No Points: 1.00 Time toComlete: 0 Difficult : 0.00 S stemID: 1455488 User-Defined ID:
Cross Reference Number:
295018 .
A2.05 To ic: ON-113 -
De raded ressure NumField 1:
NumField 2: A NRC Text Field:
Comments: Psychometrics Level of Difficulty Time Allowance SRO Knowledge (minutes)
HIGH 10CFR55.43(b)
(5)
Source Documentation Source: NewExamitem X Previous NRCExam (2017)
Modified Bank Other Exam Bank X ILT ExamBank (2114974)
Reference(s): ARC217F-5, ON-113 Learning PLOT-5035-9e Objective:
K/A System: 295018 Partial orTotal of Importance; Loss CCW SRO 2.9 K/A A2.05Ability todetermine and/or the interpret Statement:following asthey apply toPartialorTotalLossof CCW:System pressure REQUIRED NONE MATERIALS:
Notes and Comments:
Page: 6 of77 16March2020
iC 2020NRCSROExamrev0 Test ID: 332227
$Ai5Wiff2bffidfMPf/A///fJ#/F/ko&3252Mrf41A 395///////////////A&A%&WJ1981PAfa$F Thefollowing conditions exist onUnit 3:
= Thecrewisexecuting procedure T-111 "Level Restoration"
= RPVlevel is-200 inches and slowly lowering
= RPVpressure is550psig and stable
= Noinjection source isavailable
= Efforts arebeing madetorestore 'B'RHR for injection Basedontheseconditions, Adequate CoreCooling(ACC) is (1) maintained andthe Control RoomSupervisorshall (2) .
A. (1) being (2) continue toexecute T-111, "Level Restoration" B. (1) being (2) enter andexecute T-112"Emergency Blowdown" C. (1) NOTbeing (2) continue efforts torestore ACCvia submergence using T-111, "Level Restoration" D. (1) NOTbeing (2) exit T-111, "Level Restoration" andenter andexecute the SAMPs Answer: A Page: 7 of77 16March 2020
m :
2020 NRCSROExamrev0 TestID: 332227 Correct: A WhenRPVwater level cannot bemaintained above thetopof active fuelTAF(-172 inches), adequate steam flow(cooling) is established bymaintaining RPVwater level above theMinimum zero-Injection RPVWater Level (-205 inches). Operation should continue RPVlevel until isrecovered oruntil a decision ismade that ACCisnolonger assured anda blowdown wouldbe performed.
B Distractors: ACC isbeing maintained byM2IRWLbecause thereisnoinjection and thevessel isabove -205 inches.
Plausible asa blowdown would bethe next step if performed either levellowers below -205 inches, ortheRHRpump isrestored.
However, until oneof those events happens the would operators remaininthe steam cooling section ofT-111.
C ACCisbeing maintained. Plausible ifthecandidate misinterprets, based onthe question stem what constitutes ACC.A level ofless than -195 inches with injection, would not ACC,however constiture we have noinjectionavailable andcantherefore take for credit MzlRWLinthe steamcooling section ofT-111 second partiscorrect asefforts torestoreACCvia submergence will beinprogress D ACCisbeing maintained. Plausible ifthe candidate misinterprets, based onthe question stemwhatconstitutes ACCandwhere they areinT-111If after a blowdown was performed andlevel isbelow
-195 inches ACCisnot being met.Believing thatlevel cannotbe restored andmaintained above -195 SAMPs inches, an entry into isrequired.
Page: 8of77 16March2020
2020NRCSROExamrev0 Test ID: 332227 QuestionE3info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: 1.00 S stemID: 994782 User-Defined ID: ILT-2111-4-002 Cross ReferenceNumber:295031 EA2.04 Toic: ILT-2111-4-003 NumField 1: 2015NRC NumField 2:
Text Field: NRC-09-1 Comments:
Ps chometrics Level of Difficult Time RO Knowledge y Allowance minutes HIGH 10CRF55.43(b)(
5 Source Documentation Source: NewExamitem Previous 2 NRC Exam Modified Bank Other Exam Bank XILT ExamBank (2113868)
Reference(s): T-BAS (Intro); TRIP/SAMP Curves, Tables
& Limits Bases; T-111andBases Learning PLOT-2111-4 Ob'ective:
K/ASystem: 295031 Reactor Low importance:
Water Level RO/SRO 4.6/ 4.8 K/AStatement: EA2.04 -
Ability todetermine and/or interpret the following asthey apply to REACTOR LOWWATERLEVEL:
Adeuate core coolin REQUIRED None MATERIALS:
Notes and None Comments:
Page: 9of77 16March 2020
t" 2020NRCSROExamrev0 Test ID: 332227 A ST@this&&FTAfitM27tk/AWNMtivM#?&525W?f#?EW#W/alism A LOCAisinprogress onUnit 2with thefollowing conditions:
= Reactor pressure is800psig
= Drywellpressureis 22 psigandupslow Drywelltemperature is 345 degrees Fandupslow Toruspressure is20psig and upslow
= Toruslevel is15feetand up slow
- Containment Sprays have NQI been attempted from the control room curves Thefollowing arem:
1 Drywell Spray Initiation Limit(DWSIL)
- 2. Pressure Suppression Pressure (PSP)
Limit Page: 10of77 16March 2020
ii 2020NRCSROExamrev0 ID:
Test 332227
/-
DWSPRAYINITIATION LIMIT 600 550 C
L 500 0.
2 450 w
l- 400 w
350 w 300
>< 250 a 200 co 150 3
a 100 82 0 2 4 6 8 10 12 14 16 18 20 DRYWELL PRESSURE (PSIG) 11of77 Page: 16March 2020
ijj 2020NRCSROExamrev0 Test ID:332227 CURVEPC/P-2 PRESSURE SUPPRESSION PRESSURE LIMIT 32 28 55
- a. 24 w
2 20 a
m 16 . .
a w
E
- a. 12 a
D e 8 O
l- 4 0
10 11 12 13 14 15 16 17 18 TORUS LEVEL (FT) 12of77 Page: 16March 2020
2020NRCSROExamrev0 Test ID: 332227 onthese conditions, which Based oneofthe following describes the higbestprionty required operator andthereason for action this action?
A.
ACTION BASIS Spray the Torus ANDDrywell per Reduce containment pressure before T-204 "Initiation of Containment exceeding the capacity ofthe pressure SpraysUsing RHR" suppression curve B.
ACTION BASIS PerformT-112 "Emergency Reduce containment pressure before Blowdown" exceeding the capacity ofthe pressure suppression curve C.
ACTION BASIS Spray the Torus ANDDrywell per Reduce containmenttemperature dueto "Initiation T-204 ofContainment exceeding the Drywell temperature limit SpraysUsing RHR" D.
ACTION BASIS PerformT-112 "Emergency Reduce containment temperature dueto Blowdown" exceeding the Drywell temperature limit Answer: C Answer;Explanation Choice Basis orJustification Correct: C Correct action; correctreason. PerT-102, the drywell temperature limitis340degrees F,which hasbeen exceeded. Since DWsprays have notbeen attempted, thisaction should beattempted before Performing a Blowdown.
.--...---Distractors: .A Correct action, reason incorrect Although thegiven conditions require drywell sprays, andoperation isonthe safe side ofthe DWSILcurve, thePSPcurve challenge isless important than the DW/Tissue.
Plausible since theaction ofspraying the drywell will address both problems, but thereason thedrywell mustbesprayed atthis time is because ofdrywell temperature. .
B Incorrect action, incorrectreason. Plausible since a Blowdown isan action thatwould beperformed during a violation ofthePSPcurve, however the curve isnot violatedyet andisnot thehighest priority in thegivenconditions.
D Incorrect action; correctbasis. Plausible since a Blowdown could be performed for a highdrywelltemperature condition andthe drywell temperature limitisviolated.However PerT-102, since DWsprays have not beattempted, they should beattempted before performing a Blowdown.
Page:13of77 16March 2020
n a:=e me:::nme= .. = ..
2020NRCSROExamrev0 Test ID: 332227 Question 4info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoCom lete: 3 Difficul : 2.00 S stemID: 1006402 User-Defined ID: B CERT Cross Reference Number: 295028 G2.1.32 To ic: ILT2102-004 SROB CERT NumField 1:
NumField 2:
Text Field:
Comments: Ps chometrics Level of Difficulty Time SRO Knowledge Allowance
' (minutes) ----
HIGH 10CFR55.
43b 5 Source Documentation Source: NewExamItem C Previous NRCExam:
CModified BankItem DOther Exam Bank:
@ILTExamBank Referenc andBases T-102 e(s):
Learning PLOT-2102-6, -9b Objective K/A 295028High Drywell Importance: SRO S stem: Tem erature 4.0 K/AStatement:
G2.1.32 -
toexplain Ability andapply system limits and recautions.
REQUIRED embedded reference MATERIALS:
Notes and Comments:
Page: 14of77 16March 2020
x L i
2020NRCSROExamrev0 Test ID:332227 Unit 2 isinitiallyoperating at 100%power whenthefollowing conditions occur:
e Thereactor scrams due toa loss ofalloff-sitepower e Diesel Generator E-1fails tostart automatically and manually.
e 2ADCPOWER PANELLO VOLTAGE (209 C-3)isinalarm.
a 2ADCBusvoltage atPanel 20D021 (CSR) is90VDC.
Which oneofthe following identifiesa system impacted bythe above plant conditions, andthe action needed torestore the system?
A. RCICisinoperable.
RPVlevel canbemaintainedwith HPCI using RRC23.1-2, "HPCI System Operation During a Plant Event" orwith RCIC using SE-13.1-2, "RCIC Manual Operation onLoss of125/250 VDCBus2DA-W-A.
B. 2ACRDpumptripped.
Restart the 2ACRDPumpinaccordance with SO 3.1.B-2,"CRD Hydraulic System Startup with the System FilledandVented" C. 2ACoreSpray Loopisinoperable.
Place the alternate 2Abattery charger inservice inaccordance with SO57B.1-2, "125/250 VoltStation Battery Charger Operations".
D. #1Aux. Buscontrol andprotection circuitsareinoperable.
Transfer the 2Abattery charger power source from E-124-T-B to E-134-T-B in accordance with AO57B.6-2,"Transfer of125VBattery Charger 2AD003 toAlternate Power andReturn toNormal".
Answer: A Answer Explanation Choice Basis orJustification Correct: A Correct -
RCICisinoperable duetoloss ofpower butcanbe operated without DCIAWSE-13.1-2 orcanuseHPCI.
Distractors: B Plausible asthe2ACRDpumphastripped, however E-12isstill de-energized andthe 2ACRDPumpcannot berestarted duetono power available tothe E-12 bus C Plausible asthe 2A Core Spray isinoperable, however boththe normal andalternate supply tothebattery charger comefrom the samesource, which isthe E-12 bus.
D Plausible as#1Auxcontrol andprotection are inoperable-nopower available however thisevolution canonly bedone wheninMODE4 or5,asspecified inAO57B.6-2, Prerequisite 2.1, alsowiththe LOOPandfailure ofE1diesel, there isnopower supply to E-134-T-B Page:15of77 16March2020
[
2020NRCSROExamrev0 Test ID:332227 Question 5Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 3 Difficult: 3.00 S stemID: 994314 User-Defined ID:
Cross Reference Number: 295004 2.4.31 ,
To ic: ILT-1555-1 SRO NumField 1:
NumField 2:
Text Field:
Comments: This questionsatisfies the requirements of10CFR55.43(b)(5),
Ps chometrics Level of Difficulty Time SRO Knowledg Allowance 4.1 e (minutes)
Hih 10CRF55.43 b5 Source Documentation Source: NewExam Previous NRC Item Exam:
D Modified Bank COther Exam Item Bank:
@ILTExamBank Reference(s): ARC209C-3, SE-13, AO57B.6-2 Learning PLOT-1555-1 Objective:
RJA System: 295004Partial -
or importance:
Complete Loss ofD.C. RO/SRO Power 4.2/4.1 K/AStatement:
2.4.31- Knowledge ofannunciator indications, alarms, or resonserocedures.
REQUIRED NONE MATERIALS:
Notes and Comments:
Page:16of77 16March 2020
mn s 2020NRCSROExamrev0 Test ID: 332227 A AAffij$W GWfffffffy5%%3Mffj/Wfffj$$$Vff/Ai $ff([fff52%$?$$ffifib2Ffif$l$f$fd Unit 2isina refueling outage. Thefollowing conditions exist:
= Thereactor isinMode 4 a The"B" loopofRHRisblocked for maintenance The"A" and"B" loop ofCoreSpray isavailable
- TheCondensate andFeedwater systems aredrained for feedwater heaterreplacement
= CSTisnot available asaSuction for Core Spray
- The"A" RHRpumpis inservice forShutdown Cooling a Maintenance hasaWorkOrder activity tolower Torus level to10feet.
Maintenance (1) proceed with the activity.
The"A" loopofRHR (2) "Protected Equipment" perOP-AA-108-117, "Protected Equipment Program" A. (1) can (2) is B. (1) can (2) isnot C. (1) cannot (2) is D. (1) cannot (2) isnot Answer: C Page: 17of77 2020 16March
=, ,
t 2020NRCSROExamrev0 Test ID:332227 Choice Basis orJustification Correct: C Maintenance cannot proceed because lowering Torus to10feet level will INOPCore Spray andRHR.Core Spray andRHRare theTechSpec required injection system inMode4.Forthis reason maintenancecannot continue with their activity.
Per OP-AA-108-117 section 4.2RHRwould beprotected equipmentandis currently the ONLYprotected equipment asit isused forShutdownCooling.
There iscurrently noprotected equipment forinjection since since. both loopsof Core Sprayandthe 'A' Loop ofRHRisavailble for toalign injection.
This isexplained inTS3.5.4 RPVWIC,which allows RHRinSDCtocount asinjectionsource.
Distractor A Plausible ifthe candidate misinterprets that lowering Toruslevel to10feet s: will INOPALLECCS due toexceeding thevortex limit.
Second part iscorrect B Plausible ifthecandidate misinterprets that lowering Toruslevel to10feet will INOPALLECCSduetoexceeding the vortex limit.
Plausible because the "A"loop of RHR doesnot needtobeconsidered Protected Equipment forits role asan injection source, butmustbe considered Protected Equipment initsrole asShutdown Cooling. The candidate ma misinter retthe reuiredroles.
D First part iscorrect Plausible because the "A"loop ofRHRdoesnot need tobeconsidered Protected Equipment forits role asaninjection source, butmustbe considered Protected Equipment initsrole asShutdown Cooling. The candidate maymisinterpret therequired roles.
Page: 18of77 16March 2020
h 2020 NRCSROExamrev0 Test ID: 332227 Questionli6info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 1.00 S stem ID: 1110315 User-Defined ID:
Cross Reference Number: 295030 2.2.18 To ic: ILT-1529-1r-001-SRO NumField 1:
NumField 2:
Text Field:
Comments: Ps chometrics Level of Difficulty Time RO Knowledge Allowance minutes HIGH 10CRF55.43(b)(
2 Source Documentation Source: NewExamitem Previous NRC Exam Modified Bank Other ExamBank X ILTExamBank (2113878)
Reference(s): OP-AA-108-117, Tech Specs 3.5.4 and bases Learning PLOT-1529-1r Ob'ective:
K/ASystem: 295030 LowSuppression Importance:
Pool Water Level RO/SRO 2.6/3.9 K/AStatement: 2.2.18 -
Knowledge oftheprocess for managing maintenance activitiesduring shutdown operations, such asrisk assessments, work prioritization, etc.
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 19of77 16March 2020
x = e: : .. .
a ..
2020 NRCSROExamrevo Test ID:332227 SSd?fdWfWffdW4MW/MWf7//f&%iitidffMffi$h at95%power withthe 2 is Unit followingconditions:
a temperature is 139F and Drywell risingvery slowly pressure Drywell is0.75 psig andrising very slowly cooling Drywell inmaximized
- Drywell ventingisinprogress PerOT-101"HighDrywell Pressure", RCIC MO-2-13-015 isclosed with thefollowing results
= Drywell temperature is138*F andlowering slowly pressure Drywell is0.74 psig andlowering slowly Whichoneofthefollowing would bethecorrect action todirect?
A. Maintain MO-2-13-15 closed ONLY RCIC canbereestablished ifrequired for adequate core cooling B. Maintain MO-2-13-15 closed ANDde-energize the valve RCICCanbereestablished ifrequired for adequate core cooling C. Maintain MO-2-13-15 closed ONLY RCICcannot bereestablished under anycircumstances D. Maintain MO-2-13-15 closed ANDde-energize the valve RCIC Cannot bereestablished under anycircumstances Answer: B Page: 20of77 16March 2020
2020NRCSROExamrev0 Test ID: 332227 Choice Basis orJustification Correct: B Thestemindicates that MO-2-13-15 isthesource ofthe leakaswhenit was closed theDrywell parameters improved. OT-101 then states that MO-2-13-15 should remain closed andbede-energized. This istomaintain the valve closed in case anautomatic injectionsignal isreceived. Withthe valve closed and deenergized, RCICwould bedeclared inoperable andTechSpecs would beentered. Step 3.11.4ofOT-101 says tomaintain the valve closed ORas directed by shift managment. Inaccordance with thebases, this allows shift managment discretion toopen thevalve for short term activitiessuch as troubleshootin or tomaintain e uiement availabili ifneeded.
DistractoA Plausible asmaintaining theMO-2-13-15 closed would isolate theleak and rs: RCICcould beplaced into servicequickly if needed. However theprocedure states tode-energize the valve toprevent anautomatic initiation that could admit a largeamount ofsteam tocool piping. This could lead toa waterhammer event anddamage the system further.
Secondart iscorrect.
C Plausible asmaintaining the MO-2-13-15 closed would isolate theleak and RCICcould beplaced intoservicequickly if needed. However theprocedure states tode-energize thevalve toprevent anautomatic initiation that could admit alarge amount ofsteam tocool piping. Thiscould lead toa waterhammer event anddamage thesystem further.
Plausible asclosing the valve hasisolated a steam leakinthedrywell which leads toEOPentries ifre-opened. However other EOP entriesand transients could leadtoworse consequences then a high drywell pressure, such asa loss ofACC.Theprocedure states that the shift management isable touse their discretion and lant status inorder too enthe valve.
D First partiscorrect Plausible asclosing the valve hasisolated a steam leak inthe drywell which leads toEOPentries ifre-opened. However other EOPentriesand transients could leadtoworse consequences then a high drywell pressure, such as a loss ofACC.Theprocedure states that the shift management isable to use their discretion and lant status inorder too enthevalve.
Page: 21of77 16March2020
1 jr 2020 NRCSROExamrev0 Test ID:332227 Question7 Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 2 Difficult: 2.00 S stemID: 2132466 User-Defined ID: ILT-1540-4-024 Cross Reference Number: 2.4.11 .. .
To ic: SRO ILT-1540-4-024 OT-101 RCICvalve leak NumField 1: NA NumField 2: NA Text Field:
Page: 22of77 16March 2020
s 2020NRCSROExamrev0 TestID:332227 Comments: MMJrNBWfifif~!"fWQT'A i
Ps chometrics Levelof Difficul Time SRO Knowled ty Allowan ge ce (minute s
HIGH 10CFR55.43(b)5 Source Documentation Source: X NewExam item Previous NRCExam Modified Bank Other ExamBank ILT ExamBank References : OT-101 Bases Learning PLOT 1540-4 -
Ob^ective:
K/ASystem: 295024Importance; RO/SRO High 4.2 Drywell Pressur e
K/A 2.4.11 -
Knowledge ofabnormalcondition Statement: rocedures REQUIRED none MATERIALS:
Notesand This question meets 10CFR55.43 criteria Comments: asanSROquestion because consideration ofplacing systems ina lineup notaligned with their techspec required isan positions SROfunction.
Page:23of77 16March2020
2020NRCSROExamrev0 Test ID:332227 if@h2Ai%d#?b[d//NSSA&ARY///AYNAWAWA1WAW#ANN///AfffA2#2%3W Unit3isoperating at 100% power whenthe following occurs:
= AnEquipmentoperator reportsasteam leak intheUnit 3 Reactor Building
= Annunciator 317K-5, "Reac BIdg. Hi-Lo DiffPressure" alarms Annunciator 317L-1"Reac Bldg. Refueling Area Hi-Lo Diff Press" alarms GP-4 "Manual Reactor Scram"is performed onUnit 3 a RPVlevel is -25inches andsteady a 8control rods areatPosition 12 a Reactor power is1.5 EO%
a TheShift Manager hasdeclared a Site Area Emergency (SAE) for anUnisolable Main SteamLine break intheReactor Building Entryinto the Reactor Building isnecessary toperform operation ofthe TRIPS Basedonthe above the conditions, Crewshall .
A. Reduce Secondary Containment temperature/pressure usingSO 40B.1.A-2, "Reactor Building VentilationSystem Startup andNormal Operation".
B. Reduce Secondary Containment temperature/pressure usingT-222, "Secondary Containment Ventilation Bypass perT-103, "Secondary Containment Control" C. Perform a normaldepressurization perT-103, "Secondary Containment Control".
D. Perform a rapid depressurization IAWRC/P-12 ofT-101, "RPVControl".
Answer: B Page:24of77 16March 2020
n ,
2020NRCSROExamrev0 Test ID: 332227 Choice Basis orJustification Correct: B TheReactor Building willbepositive with the report ofa large steam break inthereactor building andtheHi-lo Differentialpressure alarms.T-103 "Secondary Containment Control" mustbeentered forthe highSecondary Containment pressure condition. T-103 willdrive performance ofT-222to restore RBventilation andreduce RBtemperature andpressure.
Distractor A Plausible asboth T-103 andT-101 will drive restorationofReactor Building s: Ventilation, however with RPVlevel at-25inches a Group isolation Ill is present. The action ofrestoring ventilation isthe correctactionhoweverit cannotbeperformed with thenormal procedure. TheT-103 stepdirects performing T-222, ifnecessary. TheSROcandidate mustdetermine if ventilation canbe restored without useofT-222, inthis scenario, itcannot.
C Plausible aswearein T-103, whichwith a primary system discharging into the Reactor would leadus to depressurize tolimit the force driving ofthe steam. However with the ATWS present and thereactor notshutdown (1.5% power) depressurization is not allowed.
D Plausible asentering T-101 outofT-103 isa correct actionhoweverwith three rods atposition 12RC/P-12 cannot beused toperform the depressurization. TheSROcandidate must determine based onthestatus ofrods ifa rapid depressurization canbeconducted. With the above conditions a rapid depress isnot allowed.
Page:25of77 16March 2020
! [
2020NRCSROExamrev0 Test ID: 332227 SinfoL Question Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficult: .. .
1.00 S stemID: 1120210 User-Defined ID: ILT-2103-1-006 Cross Reference Number: 295035EA2.01 To ic: ILT-2103-2-008-SRO NumField 1:
NumField 2: N/A Text Field: A Comments:
Ps chometrics Level of Difficult Time RO Knowledge y Allowance minutes HIGH 10CRF55.43 b5 Source Documentation Source: NewExamitem Previous 2 NRC Exam Modified Bank Other ExamBank X ILT ExamBank (2114427)
Reference s : T-103, T-104, T-222 Learning PLOT-5009-2b Ob'ective:
K/ASystem: 295035 Secondary Importance:
Containment High RO/SRO Differential Pressure 3.8/ 3.9 K/AStatement: EA2.01Ability todetermine and/or monitor the following asthey applyto SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment pressure REQUIRED None MATERIALS:
Notes and None Comments:
Page: 26of77 16March 2020
2020NRCSROExamrevo Test lD: 332227
%dd%6iiRidfffMifff/fiiRWildif%MWJAWAWAN#iPWAGtWf#MTf#i2MIAEKAWW Thefollowing conditions existonUnit 2following anEmergency Blowdown 5ADSvalves:
with WiderangeRPVlevel -150 inches range Narrow RPVlevel -20inches zone Fuel level indicators +60 inches level LI-86 indicator +350 inches TI2501pts126and127 475 F MtNINDICATED LEVEL MAXRUNTEMP INSTRUMENT g ggg @ jggog NARROW RANGE 10IN @ 450*F WIDERANGE -120 IR E 500*F Chosethecorrect actions basedonthe above information.
A. Raise RPVlevel to5-35 inches using theNarrow range level indicator.
B. Raise RPVlevel to5-35 inches using theWide range level indicator.
C. Raise RPVlevel tothe Main Steam lines.
D. Raise RPVinjection until RPVpressure isabove 270psig.
Answer: B AnsweVExplahat$k" E ""AT E Choice Basis orJustification Correct: B Thewide range level indicator isthe only accurate indicator.
T-101directions wouldbetoraise RPVlevel to5-35 inches.
Distracto A TheNarrow range level indicator isnotaccurate because the Minimum rs: indicator level isbelow 10inches ANDthemaximum runtemperature isabove 450F.Plausible if thecandidate misapplies implementation ofthe requirements ofDW/T-1 andbelieves that MILandMRTarenotviolated for thenarrow rane.
C RPVlevel isknown soanentry toT-116 does not exist.Plausible as candidate maymisinterpret thatasboth level instruments above areeither MRTorbelow MILthe instruments cannotbeused, andconsequential actions for level unknown mustbetaken. Aninstrument mustbebelow MinIndicated andabove level Maxrun temerature tobeconsidered inoerable.
D RPVlevel isknown soanentry toT-116 does not exist. Plausible as candidate maymisinterpret thatasboth level instrumentss areeither above MRTorbelow MILtheinstruments cannotbeused, andconsequential actionsfor level unknown must betaken. Aninstrument must bebelow Min Indicated level andabove maxrun temperature tobeconsidered inoperable.
Plausible if the candidate confuses the ACCactions ofT-116 ATWSand Non-ATWS.
Page: 27of77 16March 2020
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2020NRCSROExamrev0 TestID: 332227 Question 9iInfo ....
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: .
1.00..
S stemID: 2078625 User-Defined ID:
Cross Reference Number: 295012 2.4.47 To ic: ILT- 2102-5-005-SRO NumField 1:
NumField 2:
Text Field:
Comments: Psychometrics Level of Difficulty Time SRO Knowledge Allowance (minutes)
HIGH 10CRF55.43(b)5 source Documentation Source: X NewExamitem Previous NRCExam Modified Bank Other ExamBank ILT ExamBank Reference(s): T-102 andbases T-116 andbases Learning PLOT2102.5 -
Objective:
K/A System: 295012High Importance;-
RO/
Drywell SRO Temperature 4.2 K/A Statement: 2.4.47 -
Ability todiagnosis andrecognize trends inanaccurate andtimely manner utilizing the appropriatecontrol room reference material.
REQUIRED embedded reference MATERIALS:
Notes and This question meets10CFR43b criteria Comments: because thecandidate mustuse the chart in determining whatindicator could beused.
Then using that knowledge make a determination oftheirplace within thetrip procedures andthenextaction totake.
Page: 28of77 16March 2020
- e - e =
2020 NRCSROExamrev0 Test ID: 332227 j$@Jp$5$ff fffffjffj ffffffffffQ7fffjjjfMJfffffjjQfffff(ffffffjQfffjf$fgg$[M,j$j$21 3isat85%power Unit when the following occurs:
AO-3-01A-080A "Inboard MSIV" drifts closed.
Basedonthe above, the crew shall A. maintain Reactor power until the MSIVcanbere-opened usingSO1A.7.D-3 "Isolation ofOneMain Steam Line atPower".
B. maintain Reactor poweruntil theMSIV canbere-opened usingSO1A.7.B-3, "Main Steam Line Recovery" C. enter OT-102, "Reactor High Pressure" andreduce Reactor Power untilReactor Power isless than 65%RTP D. enter OT-102, "Reactor High Pressure"and reduce Reactor Power untilReactor Power isless than 75%RTP Answer: C AnswerExplanationeA Choice Basis orJustification Correct: C Reactor power of85%ishigher than three mainsteam linescanpass and will result inRPVpressure rising. Therise inRPVpressure from 85%is enough foranoperator toenter OT-102. Thefollow-up action inOT-102 is lower Reactor power low enough tore-establish the margin to the Main Steam Line high flow isolation. Reducing reactor power to65% (based on 4016MWth) ensures that each steam line flow isreduced back to maintaining themaximum individual value usedinthesafety analysis (based on3514 MWth)
A Plausible since the SO1A.7.D-3 for isolating aMSIVatpower does contain a restoration section (4.3) toreopen theMSIV, however this procedure would not beused during atransient andoneoftheprerequisites istohave power less than orequal to65%.
B Plausible since the SO1A.7.B-3 isthecorrect procedure forreopening the closed MSIV,however the candidate mustunderstand that three Main Steam lines cannot support 85%reactor power without reactor pressure rising. Reactor power mustbelowered, notmaintained.
D Plausible ifthe candidate simply applies a logic 3outof4 valves that can maintain 75%power, which istrue, however itdoesnot meetour safety analysis for the closure ofoneMSIV which is stillbasedona power level of 3514MWt.Thesafety analyses only supports MainSteam Line isolation at a power level ofupto75%of3514MWt(2635.5 MWt)which relates conservatively to65%of4016MWt.
Page: 29of77 16March 2020
j 2020NRCSROExamrev0 Test 332227 ID:
Questionjj0!Info A ...
....... A .... A ... 1 ...... L Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult
- 1.00 S stem ID: 1109936 User-Defined ID:
Cross Reference Number: 295020AA2.04 To ic: ILT-5007G-5 -001 NumField 1:
NumField 2:
Text Field:
Comments: Ps chometrics Level of Difficult Time SRO Knowledge y Allowance minutes HIGH 10CRF55.43(b)(5 Source Documentation Source: NewExamitem Previous 2 NRC Exam Modified Bank Other ExamBank X ILTExamBank (2114423)
Reference s : OT-102 Learning PLOT5007G-5g-001 Ob'ective:
K/ASystem: 295020 Inadvertent Importance:
Containment IsolationRO/SRO 3.9/3.9 K/AStatement: AA2.04Ability todetermine and/or interpret the following asthey applyto INADVERTENT CONTAINMENT ISOLATION: Reactor ressure REQUIRED None MATERIALS:
Notes and This meets therequirements of Comments: 10CFR55.43(b)(5) asthe answer be cannot obtained bysolely knowing immediate operator actions andmusthave knowledge ofhowtoim lement theracedure.
Page: 30of77 16March 2020
=s ,<
2020NRCSROExamrev0 Test ID: 332227 AjLjk%%$$ffffM$$92diQfflfffAi)ffffjfjfjj$$jffff)WMiffli$Wffkif$&%$j$ffj$jjl$fA&ANE Giventhefollowing:
- A lossofoff-site power hasoccurred.
- TheCrewisperformingSE-11, "LossofOff-Site Power".
SE-11 Attachment A,"DieselGenerator Lockout from the Main Control Room" hasbeen performed on theE-1, E-2andE-3Diesel Generators.
a TheE-22, E-23 andE-33 breakers are inoperable andcannot beclosed.
- TheE-4Diesel Generatorwillnot start.
PerSE-11, what Sheet should beentered andexecuted forthe conditionslisted?
A. SE-11 Sheet6"Extended Loss ofACPower (ELAP)"
B. SE-11 Sheet4"Loss ofOff-Site Power with Only 1 D/GAvailable" C. SE-11 Sheet3"Loss ofOff-Site Power With Only 2 D/Gs Available" D. SE-11 Sheet2 "Loss ofOff-Site Power With 3orMore D/Gs Available" Answer: C Answer:Ex lanationBe E . .. PC 1 . .... xn .. A .. . ..
Choice Basis orJustification Correct: C PerSE-11, D/Gs that have been shutdown duetoa lack ofcooling (which is thepurpose ofSE-11 Attachment A), but arecapable ofback-feeding an operable ESWorECWpump, should becounted asavailable . Therefore, theE-1andE-3D/Gs areavailable andSheet 3would beentered.
Distractor A Plausible because theE-1, E-2andE-3were shutdown. If the candidate s: misinterprets what makes anoperable D/Gandbelieves that if a D/Gis shutdown itisnotavailable thiswould bethecorrect answer. However, E-1 andE-3D/Gs have operable output breakers andthey areavailable even thou hthewere shutdown.
B Plausible ifthecandidate misinterprets that theE-3D/Gisnot available because oneofits output breakers isnot available. E-1andE-3are available because they haveoperable output breakers.
D Plausible if candidate misinterprets the start oftheE-1, E-2, andE-3diesels asbeing able toconsider themall operable, however duetoboth output breakers onE-2Diesel generator being INOPonly E-1andE-3D/Gare available.
Page: 31of77 16March 2020
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2020NRCSROExamrev0 Test ID: 332227 Question 11!Info! A Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficul : 1.00 S stemID: 1140429 User-Defined ID:
Cross Reference Number: 264000 A2.09 To ic: ILT-1555-3-24-SRO-SE-11 NumField 1:
NumField 2:
Text Field:
Page: 32of77 16March 2020
= , ,.
2020 NRCSROExamrev0 Test ID:332227 Comments: Ps chometrics Level of Difficulty TimeAllowance RO Knowled e minutes HIGH 10CRF55.43(
b2 Source Documentation Source: NewExamitem Previous 2 NRCExams Modified Bank Other Exam Bank X ILT ExamBank639215 Reference(s SE-11 andbases Learning PLOT-1555-9, 11 Ob'ective:
K/ASystem: 264000 -
Emergency Importance; Generators (Diesel/Jet) RO/
SRO 3.7 /
4.1 K/A A2.09Ability to (a)predict the impacts ofthe Statement: following ontheEMERGENCY GENERATORS (DIESEL/JET) ;and(b) based onthose predictions, useprocedures to correct, control, ormitigate the consequences ofthose abnormal conditions or operations:
Loss ofA.C.ower REQUIREDNone MATERIAL S:
Notes and This question isdesignated asSROONLY Comments:because:
a It cannot beanswered byknowing immediate operator actions ofTRIPentry conditions (must knowfollowup actions).
a It requires recall ofa strategy oraction that iswritten into a plant procedure, including whenthe strategy oraction is taken.
a It isanSROjob function todetermine the SE-11 requirements andconditions for howthe Loss ofOff-site power affected D/Gavailability.
a TheSROwould then usethis information tochoose the correct procedure to miti ate theevent Page:33of77 16March 2020
e n := ,,,. . .. 7 n n 2020 NRCSROExamrev0 Test ID:332227 2l$15AAT% hi&if/A7/fiff121dffk 7/MMA#f fW/fAff##fMWii)A Unit2 hasexperienced a Loss ofOff-site Power (LOOP). Thefollowing conditions arepresent:
a Thereactor isshutdown.
a RPVpressure is1000 psig andrising.
a RPVlevel is -30inchesand lowering.
a GroupI,II, andIll isolations have gonetocompletion.
a AIIDiesels have automatically started andare supplying their associated buses.
a AO-2969A "ADrywell" andAO-2969B "BDrywell" have nolight indication if trends current continue, with nooperator action:
TheADSvalves initiallywill-(1)- ona valid ADSinitiation signal.
(2) must b edirected toopen and/or support long term ADSSRVoperation.
A. (1) NOTOPEN (2) SO16A.7.A-2 "Backup Instrument Nitrogen to ADSSystem Manual Actuation" B. (1) NOTOPEN (2) GP-8.E "Primary Containment Isolation Bypass" instrument N2Supply section C. (1) OPEN (2) SO16A.7.A-2 "Backup Instrument Nitrogen toADSSystem Manual Actuation" D. (1) OPEN (2) GP-8.E "Primary Containment Isolation Bypass" Instrument N2 Supply section Answer: C Page: 34of77 16March2020
2020NRCSROExamrev0 Test ID: 332227 Choice Basis orJustification Correct: C ADSvalves would open duetotheir accumulators. SO16A.7.A-2 orRRC 16.1-2 would needtobeused. Thissupplies nitrogen directly fromthebottles to theADSvalves. Bypassing theprimary containment would isolation supply all N2 valves in the drywell through both headers ofinstrument nitrogen, however AO-2969A "ADrywell" andAO-2969B "BDrywell" have nolight indication and cannotberepositioned tobypass. Therefore GP-8.E willnot su I valves inthe D ell.
Distracto A Valves would open due totheir accumulators, plausible asnot allSRVvalves rs: have accumulators.
Second art iscorrect B Valves would opendue totheiraccumulators, plausible asnotall SRVvalves have accumulators.
Plausible asGP-8.E isused inmostscenariosandbypassing theprimary containment isolation would supply all N2valves inthedrywell throughboth headers ofinstrument nitrogen, however AO-2969A "ADrywell" andAO-2969B "BDrywell" havenolight indication and cannot berepositioned tobypass.
Therefore GP-8.E willnot su I valves inthe D ell.
D First part iscorrect Plausible asGP-8.E isused inmost scenarios andbypassing theprimary containment isolation would supply allN2valves inthe drywell throughboth headers ofinstrument nitrogen, however AO-2969A "ADrywell"andAO-2969B "BDrywell" have nolight indication andcannot be repositioned tobypass.
Therefore GP-8.E willnot su I valves inthe D ell.
Page: 35of77 16March 2020
ji 2020NRCSROExamrev0 Test ID: 332227 Question 12info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized forractice? No Points: 1.00 Time toComlete: 3 Difficul : 2.00 S stemID: 2131129 User-Defined ID: ILT-5001G-6D-002 Cross Reference Number: 218000A2.03 ILT-5001G-002 ADSwithoutN2su I inst NumField 1:
NumField 2: NA Text Field: B Page:36of77 16March 2020
2020NRCSROExamrev0 TestID:332227 Comments: WWEfA: W"0:W'"fili N'W'"'til iii Levelof ii Difficul Ps chometrics Time SRO Knowled ty Allowan ge ce (minute s
HIGH 10CFR55.43(b) 5 Source Documentation Source: NewExam item Previous NRCExam X Modified Bank (994169) Other ExamBank ILTExamBank References : T-101',SO16A.1.A-2;T-261 Learning PLOT 5001G-6d -
Ob'ective:
K/ASystem: 218000 -
Importance; RO /
Automatic SRO Depressurizatio 3.6 nS stem K/A A2.03Ability to(a) predicttheimpactsof Statement:thefollowing on theAUTOMATIC DEPRESSURIzATION SYSTEM ;and(b) based onthose predictions,useprocedures tocorrect, ormitigate control, the consequencesof thoseabnormal conditions oroperations:
Lossofair su I toADSvalves:
REQUIRED none MATERIALS:
Notesand Thisquestion meets theK/Aand Comments: 10CFR55.43 criteria the bytesting of ability theSROtomakea proper of evaluation plant status andthen choose the correct rocedure tomiti ate the event.
Page:37of77 16March2020
Cj /at)
F///AfWE////E///E/////E//W//////E////E////EE/#Wa Unit 2hasexperienced a Loss ofOff-site Power (LOOP). Thefollowing are conditions present:
The reactor isshutdown.
RPV pressure is1000 psig andrising.
RPV level is-30inches andlowering.
GroupI, II, and III isolationshave gone tocompletion.
All Diesels have automatically started andaresupplying theirassociated buses.
Asconditions deteriorate, with nooperator action:
(1) describe the response of theADSvalves toavalid ADSinitiation, AND (2) provide the a ction necessary to allow valve operation and/or support longtermADSoperation.
TheADSvalves initially would (1). .
(2) must be directed to open and/or support long termADSSRVoperation.
A. (1) NOTOPEN (2) SO16.1.A-2, Inst Nitrogen System Startup andNormal Operations B. (1) NOTOPEN (2) T-261, Placing the Backup Inst Nitrogen Supply from CADTank inService C. (1) OPEN (2) SO16.1.A-2, Inst Nitrogen System Startup and NormalOperations D. (1) OPEN (2) T-261, Placing theBackup Inst Nitrogen Supply from CADTank inService Answer: D fMbdWd/dd@l@2Tdf/dif@DD Choice Basis orJustification Correct: D Valves would openduetotheir accumulators. T-261isrequiredfor long term o eration Distracto A Valves would open duetotheir accumulators, plausible asnot allSRV valves rs: have accumulators. Plausible asSO16.1.A-2 isachoicetorestore instrument nitro en,however itcannot bestarted normall dueto1"isolation sinal.
B Valves would openduetotheir accumulators, asnotall plausible SRVvalves have accumulators.
T-261 isreuired for lontermo eration.
C Valves would open duetotheir accumulators.
Plausible asSO16.1.A-2 isa choice torestore instrumentnitrogen,however it cannot bestarted normall dueto1"isolation sinal.
PB-OPS-EXAM-ILT-2015 Page: 1of4 12March 2020 Current View
fWW/2bffA262F/12f?//@@dB23ff/ddid33 Question T e: MultileChoice Status: Active Alwasselect ontest? No Authorized for ractice? No Points: 1.00 Time to Comlete: 3 Difficult : 2.00 m, ~rrrr,,,,em
- > ,m,-am--::=m-zm-,m, w. .
,-mamn:mn S stem ID: 994169 User-Defined ID: ILT-5001G-6D-001 Cross Reference Number:
wo-m:m,,,,mv,,,arrsmmememumnnumw,,,mmwwg-nnsw:m 218000A2.03 To ic: ILT-5001G-001 ADSwithout Inst N2su I NumField 1:
NumField 2: NA Text Field: B PB-OPS-EXAM-lLT2015 2 of4 Page: 12March 2020 Current View
Comments: //4#/L :"~"'"'"""'~*'**'1I'''""';
" ~
/
Pschometrics Level of Difficul Time SRO Knowled ty Allowan ge ce (minute s
HIGH 10CFR55.43(b) 5 Source Documentation Source: NewExamitem Previous NRCExam Modified Bank Other Exam Bank X ILT Exam Bank Reference s : T-101; SO 16A.1.A-2; T-261 Learning PLOT 5001G-6d-Ob'ective:
K/ASystem: 218000 -
Importance; RO/
Automatic SRO Depressurizatio 3.6 nS stem K/A A2.03Ability to(a) predict theimpacts of Statement:the following on the AUTOMATIC DEPRESSURIzATION SYSTEM ;and(b) based onthose predictions, useprocedures tocorrect, control, ormitigate the consequences of those abnormal conditions oroperations:
Loss ofair su I toADSvalves:
REQUIRED none MATERIALS:
Notes and This question meets theK/Aand Comments: 10CFR55.43 criteriabytesting the abilityof theSROtomakea proper evaluation of plant status andthen choose the correct rocedure tomiti atetheevent.
Ref:
4.6 PB-OPS-EXAM-ILT-2015 Page:
3of4 12March 2020 View Current
Associated objective(s):
7d.Determine theeffectaloss that ormalfunctionofthe following will onthe have ADS:
Pneumatic toADSvalves supply PB-OPS-EXAM-ILT-2015 4 of4 Page: 12March 2020 Current View
= = .. m ii 2020NRCSROExamrev0 Test ID: 332227 j%%%$
A$)jlj fffifff/ff$$$5ffffffhffj$j((ff%$[f[ffkf/j$$ $jl$$A$$1 Ai 8977/////fA$fffffA$&ff///Af 2isat100%power Unit ofOff-site Loss power occurs a Only1D/Gisavailable
= ToconserveCSTinventory both RCICandHPCI suctionshave swapped been tothe Torus 50minutes the into event
= TorusTemperature isreading 181F and rising Regarding sources, suction theCRSwoulddirect theROto:
A. Continue torunHPCI onTorussuction And Continue torunRCIC onTorus suction B. Continue torunHPCIonTorus suction And SwapRCICsuction back toCSTinaccordancewith SO13B.7.A-2 "Transfer ofRCIC PumpSuction from CSTtoTorus" C. SwapHPCIsuction back toCSTinaccordance SO23.7.B-2 with "Transfer ofHPCI PumpSuction from CSTtoTorus" And Continue torunRCIC onTorus suction D. SwapHPCI suction back toCSTinaccordance SO23.7.B-2 with "Transfer ofHPCI PumpSuction from CSTtoTorus" And SwapRCICsuction back toCSTinaccordance SO13B.7.A-2 with "Transferof RCIC PumpSuction from CSTtoTorus" Answer: C Page: 38of77 16March2020
j 2020NRCSROExamrevo Test ID: 332227
<<Choice Basis orJustification Correct: C inaccordance withSE-11 sheet 4,HPCIshould onTorus remain suction untilTorus temperature reaches above 180Fandthen use the CSTfor suction.
Distractors: A Plausible because inSE-11 sheet 4 both HPCIandRCICare swapped to Torus suction inordertoconserve CSTinventory and should remain thereuntil touseTorus unable anylonger.
suction HPCI maximum temperature torun onTorus suction is180Fand it must beswapped back toCSTtoprevent damage RCIC remaining onTorus suction iscorrect.
B Plausible because in SE-11 sheet 4 both HPCIandRCICare swapped toTorus suction inordertoconserve CSTinventory and should remain there until unabletouseTorus anylonger.
suction However, HPCI maximum temperature torun onTorussuction is 180Fandit must beswapped back toCSTtoprevent damage Plausible since HPCI and RCIC need tobereturned toCST suction however RCIC can run onTorus suctionupto215Fand the candidate mayrnisapply the2temperatures.
D HPCIswapiscorrect Plausible since HPCIandRCIC need tobereturned toCST suction however RCICcanrunon Torus suction upto215Fand the candidate ma misa I the2 tem eratures.
Page: 39of77 16March 2020
2020NRCSROExamrev0 Test ID: 332227 Question'i3 Info + ' ' ' ' ' '
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2131141 User-Defined ID:
Cross ReferenceNumber:206000 21.20 To ic: ILT-1555-3-32 SROSE-11 HPCIwith 1DG NumField 1:
NumField 2:
Text Field:
Page: 40of77 16March 2020
2020NRCSROExamrev0 Test ID:332227 Comments: P
/
Level of Diffi Time
/
Pschometrics RO Knowle cult Allowa dge y nce (minut es Memo 10CRF55.43 b5 Source Documentation Source: X NewExam Previous NRCExam item Modified Bank Other ExamBank ILTExamBank Referen SE-11 sheet 4 ces :
Learnin PLOT-1555 9
Objecti ve:
K/A 206000High Importance:
SystemPressure RO/SRO Coolant 4.6 Injection S stem K/A 2.1.20-Ability tointerpret andexecute procedure Statem steps ent:
REQUI None RED MATER IALS:
Notes This question meets theK/Afor 10CFR55.43 for and anSROquestion because the stepsbeing Comme performed are notinthegeneral path flow ofan nts: EOPandare withina specific ofanSE sheet procedure. Thecandidate must the interpret conditions andmakeadecision that entails HPCI o erations.
Page:
41of77 16March 2020
nSn,,, ;m
@@ b 2020NRCSROExamrev0 Test ID:332227 ADD#YWffffffAffWd/fAWMff/lhW/fffdbfth2ik Unit 2isat100% power whenthe following occur:
= 203D-4"Condensate Transfer PumpLowDisch Press" Alarms
= 224A-4"ACore SprayLine Vent Accumulator LowLevel" Alarms
= 2 CSTandUnit Unit 3CSTlevels are34feet andsteady
= Pl-2-14-048A"'A'LoopCore Spray Discharge" isreading 25psig andlowering
- Pl-2-14-048B"'B'LoopCore Spray Discharge" isreading 80psig andsteady
- AnEquipment Operator sent toinspect the condensate transfer pumpreports that it isrunning with no issues a ST-O-014-350-2 "CoreSpray LoopA Valve Alignment and Verification" FilledandVented was completedUNSAT Using theindicationsgiven:
Loop The'A' Core Spray should beconsidered --(1)--
AND RoomSupervisor TheControl should direct --(21 A. 1)OPERABLE 2)starting the second condensate transfer pumpinaccordance with SO 27.1.A "Condensate Transfer andStorage System Startup andNormal Operation" B. 1)OPERABLE 2)performing ST-M-014-601-2, "ACore Spray Loop Filled AndVented Verification" C. 1)INOPERABLE 2)starting the second condensate transfer pumpinaccordance SO27.1.A with "Condensate Transfer andStorage System Startup andNormal Operation" D. 1)INOPERABLE 2)performing ST-M-014-601-2, "ACore Spray LoopFilled AndVented Verification" Answer: D Page: 42of77 16March 2020
2020NRCSROExamrevo Test ID: 332227 Choice Basis orJustification Correct: D Inaccordance with ARC224A-4, the 'A'loop ofCore Spray would be considered INOPERABLE. This canbeconcluded bythefact thatthe Discharge Pressure islowering indicating a leak inthepiping. This accompanied bythe vent accumulator lowlevel alarm indicatingthe'A' Loop Core Spray piping isnot fullandcompleted ST-O-014-350-2 UNSAT will make
'A'loop Core Spray bedeclared INOPERABLE.
Inaccordance with ARC224A-4, ST-M-014-601-2 mustbeperformed priorto declarinthe 'A'CoreS rao erable a ain.
Distracto A Plausible asin accordance with ARC224A-4, the'A' Core Spray Loopis rs: operable until evidence exist that the discharge piping didnot remain full.
However thereisevidence shown with the discharge head lowering as compared tothe 'B'Loop Core Spray that hasa normal discharge head pressure andanUNSAT ST-O-014-350-2.
Plausible asARC-203 D-4 is associated with a problem inthe condensate transfer system. However with the pump running with noissues, anda clear leak within the 'A' loop ofCoreSpray, starting a second pumpwould not solve theproblem. Also the SOlisted is used toonly startonepumpandit would be anabnormal ali nment tohave bothcondensate transfer um srunnin .
B Plausible asinaccordance with ARC224 A-4, the'A' Core Spray Loopis operable evidence until exist that the discharge piping didnotremain full.
However thereisevidence shown with the discharge head lowering as compared tothe 'B'Loop Core Spray that hasa normal discharge head pressure andanUNSAT ST-O-014-350-2.
Secondart iscorrect.
C First part iscorrect Plausible asARC-203 D-4isassociated with a problem inthe condensate transfer system. However with thepumprunning with noissues, and aclear leak withinthe 'A' loop ofCore Spray, starting a second pumpwould notsolve theproblem. Also the SOlisted isused toonly startonepumpand it would be anabnormal ali nment tohave both condensate transfer um srunnin .
Page:43of77 16March 2020
2020NRCSROExamrev0 Test ID:332227 Questionf4 Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2130316 User-Defined ID: ILT-5014-6F Cross Reference Number: 209001 2.4.45 To ic: SRO -
CSlow accumulator alarms NumField 1:
NumField 2:
Text Field:
Page:44of77 16March 2020
2020NRCSROExamrev0 Test ID: 332227 Comments:
i
/
// Pschometrics Level of Difficult Time SRO Knowledg y Allowanc e e minutes HIGH 10CFR55.43(b)5 Source Documentation Source: X New Exam item Previous NRCExam ModifiedBank Other ExamBank ILTExamBank Reference s : ARCs224A-4, 225 C-4, 203D-4 Learning PLOT 5014-6f -
Ob'ective:
K/ASystem: 209001 Importance; RO /SRO Low 4.3 Pressure Core Spray S stem K/A 2.4.45 -
Abilitytoprioritize the andinterpret Statement:sinificance ofeachannunciator oralarm.
REQUIRED none MATERIALS:
Notes and This question meets theK/Aand Comments: 10CFR55.43 criteria bytesting theability of theSROtomakea proper evaluationof s stemstatus.
Page:45of77 16March2020
2020 NRCSROExamrev0 Test ID: 332227 Kh?TWhM /fhM$$$6$$Mf#%rW/////ff%f%E#vAAA Unit3isat100% power withnotesting inprogress Unit2isat100%power 2 days followinga refueling outage. conditions Thefollowing exist:
a Fuelbundles arebeing moved intheUnit 2fuel pool for inpreparation ofanISFSI loading cask a ST-O-09A-325-2, "StandbyGas Treatment (SBGT) Subsystem Operabilityisinprogress Test" a SBGTFanruns "B" for 10minutes during testing andthen onovercurrent trips Fortheaboveconditions, (1)WhatistheTechnical Specification required action forUnit 2?
AND (2)WhatistheTechnical Specification required action forUnit 3?
A. (1) Entera PotentialTS3.6.4.3 (2) Entera PotentialTS3.6.4.3 B. (1) Entera PotentialTS3.6.4.3 (2) RestoreSBGT subsystem tooperable in7days.
C. (1) RestoreSBGTsubsystem tooperable in7 days.
(2) Entera PotentialTS3.6.4.3 D. (1) RestoreSBGTsubsystem tooperable in7days.
(2) RestoreSBGTsubsystem tooperable in7 days.
Answer: D Page: 46of77 16March 2020
2020 NRCSROExamrev0 i
Test ID: 332227 Choice BasisorJustification Correct: D The"B" SBGTfan tripped onovercurrent making thefan INOPERABLE.
This fan islistedinthe bases ofTech Specs aspart ofa subsystemfor both Unit 2 andUnit 3.SBGTisacommon system withtworedundantfilter trains. Thefilter trains arecommonfor both however units, the'A'SBGT fan isrelated toUnit 2 and'C' SBGTfan isrelated toUnit3.The'B' SBGT fan isthesecond operable fanfor BOTHunits. Therefore ofthe'B' a loss SBGT fanwould cause a lossofonesubsystem oneachunit.
Distractor A Plausible as theSBGTsystem iscommon toboth units.Thecandidatemay s: misapplythis knowledge that since there arestill 2 SBGTfans available (A
andC) andboth trains are still functioning that theymeettheTechSpec criteria ofhaving 2 SBGT subsystems operable. However thereisone o erable forUnit2 and oneo erable for Unit 3.
B Plausible asalthough SBGT system iscommon toboth Unitsandsharea lot ofcomponents, certain components are specifictoa unitandthe candidate maymisapplywhat component relates towhat This unit. wouldbe correct ifthe'C'fan triedon overcurrent.
C Plausible asalthough SBGTsystem iscommon toboth Unitsandsharea lot ofcomponents, certain components arespecifictoa unit andthe candidate maymisapply what component relates to what This unit. wouldbe correct ifthe'A'fan tripped onovercurrent.
Page: 47of77 16March 2020
e 2020NRCSROExamrev0 Test ID: 332227 Question46Mfo!
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficul : 1.00 S stem ID: 2131209 User-Defined ID: ILT-5009A-14-002 Cross Reference Number: 295017 2.2.12 To ic: ILT-5009A-14-002-SRO 'B' SBGTFanTri NumField 1:
NumField 2:
Text F ield:
Comments: Psychometrics Level of Difficulty Time RO Knowledge Allowance minutes HIGH 10CRF55.43(b)(
2 Source Documentation Source: X NewExamitem Previous NRC Exam Modified Bank Other ExamBank ILTExamBank Reference(s): Tech Spec 3.6.4.3Unit2 and Unit 3,Tech SpecBases, ST-O-09A-325-2 SBGT SubsstemO erabilit Test Learning PLOT-5009A-14 Ob'ective:
K/ASystem: 261000Standby -
Gas Importance:
Treatment System RO/SRO 3.0/3.1 K/AStatement: Ability following (a) to predict ontheSTANDBY theimpacts GAS ofthe TREATMENT SYSTEM ;and(b) based on those predictions, useprocedures to correct, control, ormitigate the consequences ofthose abnormal conditions oro erations: Fantris REQUIRED TechSpecsection 3.6.4.3 (SBGT MATERIALS:S stemUnit 2andUnit 3 Notes and None Comments:
Page:48of77 16March 2020
b @j 2020NRCSROExamrev0 Test ID: 332227 4AbA t$iiidhittitWistdtd2$5iMRWAfrB13Af352MWhkaW7/F//N#fJ/7//fiWtrAssistffaian Thefollowing conditions exist onUnit 2
- A steam leak inthe Drywell exists
= Pressure SuppressionFunction isLost a Reactor pressure is550psig and steady a Torus temperature is 2000F andrising slowly a Torus level is13ft andsteady
- A andC RHRpumps areinTorus Cooling a Drywell Sprays arecurrently inservice using theB RHR pump a Drywell pressure is5 psig andslowly rising BRHRpumpAmpsare oscillating a FI-136B "Test/Spray" isoscillating between 10,000 and10,500 gpm Below isT-102 "Primary Containment Control" sht 3for Torus level 12.3 feet to 13.64 feet r 1!i ij !ju !m i11/ 1!t: 1!i! A E W M!l!!!!!!!!!!!! TORUSPRESSURE 300 4A4~ W !l!! !!)!W -ht1.upp 12,.+4-;g ;-g++44+44u. J-g.p.
l!!! !!!! !!!!p.41
-a -a !!! 44t-4~
~4-4E
- p ag+g+.
- .w+
-i-H-L- ; 60 PSIGAND ABOVE e
- !l[ p.w ;!;!uu !l!l l!wl; ll; >
l ;!ll ;pl!! ;;l;.-;-w.
- x : :
m
- l l' '
" i"
- 4 ;
W Wh ~tttt > .
p+.p
- ;;;!
- /
- ;;;i ,
250 : r : :: : 1 r;: : : : ::: [:3 ; : 30TO59.99 PSIG a : , . , : , : ,
rr-rnr y, o, :
C j m2 A: a 20TO29.99PSIG
, , , , > < > > 3t t [n njata a , , , . , < , , ,
- : , , , c , , ... .
2 200 M f ;E; ;;;; ;;1; ; ; l; ;
- ;
- :: ;'Ii-; : ;l ml U-R 10TO19.99
-W44 ; :i lH-i-i4+-i (11 '
h 4 lh + PSIG i- ;l!i !; ! !! :;~W- '
W jjjj E A ? !;!l W W !; 1+ A :U 6 TO0.99PSIG g ~Hjj~ Q jj!;J '4 gr 150 ;
fp
. 1, : : , ,, , , , , , , , , ,
Q b
,,,-, ,,,,- n ,,,,,, -,, ,,
jjj...[ jjjj..jjjj
+++-++++-:-s-:-++::
4-j.j..j......j.j.j-[-j-jp
-+.+++ :
-j-j-j~ j.,j-ljj.'-
.Q j-[-.j-j-j-j
+ :
Jjjj.pQj-4pje-
-j.-jp
.gA +jp-pqj.Ap-qq-j4 g 4Jj+44 . . .
444 g-pg+ pppy 50
.j-;-pp p.pjp jj-jp Jpj.7 q-j.jp 4jpj. -j+j4 -ppjp pg4-g-j.-jj.j4jp1F +M-FMF0 TO2.99PSIG 5,000 6,000 7,000 8,000 9,000 10,000 11,000 12,000 1PUMP 10,000 12,000 14,000 16,000 18,000 20,000 22,000 24,000 2 PUMPS RHRLOOP FLOW (GPM)
Page: 49of77 16March 2020
2020NRCSROExamrev0 Test ID:332227 Forthe aboveconditions, choose the statement below that correctly describes theappropriate Torus pressure bandand select the appropriateprocedural guidance forTorus level recovery.
Torus pressurebandper T-102 should be-(1).- andTorus level is toberestored using A.
A. 1) 3 5.99 psig
- 2) "HPSW Injection T-231 into theTorus" B. 1) 3 5.99 psig
- 2) T-233 "CSTMakeup tothe Torus via HPCIMinimum Flow Line" C. 1) 6 9.99 psig 2)T-231 "HPSWInjection into the Torus" D. 1) 6 9.99 psig
- 2) T-233 "CSTMakeup tothe Torusvia HPCI Minimum Flow Line" Answer: D Answer Explanation Choice Basis orJustification Correct: D TheBRHRpump isexperiencing cavitation due toinadequate net positive suction head asindicated bythe oscillating amps and flow. A Torus pressure band of6 9.99 feet would increase Netpositive suction headonthe RHR pumpsandprevent cavitation. This pressure band would putyou onthe safe side ofthe T-102curve.
T-233 "CSTMakeup tothe Torus viaHPCIMinimum FlowLine" would beused toraise torus level. Although T-231 "HPSW injection into theTorus" has more flow availabletoinput intothetorus uses it theB loop RHRpiping to inject into theTorus. TheB loop ofRHRiscurrently being used forDrywell Sprays and cannot beused toinject intothe Torus. Since torus levelissteady, there isnot anurentneed for the additional flow.
Distracto A First part isplausible asthis isthenormal level band givenwhencontrolling rs: Drywell pressure with Drywell Sprays andDrywell pressure would affect Torus pressure. However this pressure bandwould putusontheunsafe side ofthe T-102 curve.
Second part isplausible asT-231 "HPSW injection into theTorus" hasmore flow availabletoinput intothe torus however ituses theB loop RHRpiping to inject into theTorus. TheB loop ofRHRiscurrently being used forDrywell Sprays andcannot beused toinject intotheTorus. Since torus level issteady, there isnotanurentneedfor theadditional flow.
B First part isplausible asthis isthenormal level band given whencontrolling Drywell pressure with Drywell Sprays andDrywell pressure would affect Torus pressure. However this pressure band would putusonthe unsafe side ofthe T-102 curve.
Secondart iscorrect C First part iscorrect Second partisplausible asT-231 "HPSW injection into theTorus" hasmore flow availabletoinput intothe torus however ituses the B loop RHRpiping to inject into theTorus. TheB loop ofRHRiscurrently being used forDrywell Sprays andcannot beused toinject intothe Torus. Since torus level issteady, there isnotanurentneed for the additional flow.
Page:50of77 16March 2020
2020 NRCSROExamrev0 Test ID:332227 Questionite;lnfo .
Question T e: Multi leChoice Status: Active Alwasselecton test? No Authorized forractice? No Points: 1.00 TimetoComlete: 0 Difficult
- 2.00 S stem ID: 2130211 User-Defined ID: PLOT-5010-10L Cross Reference Number: 226001 A2.01 To ic: SRO RHR cavitation ond ell s ras NumField 1:
NumField 2:
TextField:
Page:51of77 16March 2020
2020NRCSROExamrev0 Test ID:332227 Comments: T-102 sht3 RHRcurve with Toruslevel12.3ftto 13.64ft
//ii Pschometrics Level of Difficul Time SRO Knowled ty Allowan ge ce (minute s
HIGH 10CFR55.43(b) 5 Source Documentation Source: X New Exam item Previous NRCExam Modified Bank Other ExamBank ILTExamBank Reference s : T-102 sht 1,3andbases Learning PLOT 5010-101 -
Ob'ective:
K/ASystem: 226001 Importance;-
RO /SRO RHR/LPCI: 2.6 Containme ntSpray System Mode K/A Statement:the A2.01Ability following (a) to predict on theimpacts of theRHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE;and(b) based onthose predictions, useprocedures tocorrect, control, ormitigate theconsequences of those abnormal conditions oroperations:
Inade uate netositive suction head REQUIRED T-102 sht 3 RHRcurve withTorus level MATERIALS:12.3ft to13.64ft Notes and Comments:
Page:52of77 16March2020
2020NRCSROExamrev0 Test ID: 332227 154%id$ib$$$f&$$54f$)Wf)fA$5%Wik$$$%[%(($Fdffhj$4 Unit2Traversing In-Core Probe (TIP) System operation isinprogress foranLPRMcalibration.
A subsequent Feedwater transient results inthefollowing conditions:
= TheReactor wasmanually scrammed e RPVlevel lowered to-10 inches andisnowat+20inches
= Thein-service TIPdetector isin the core.
Which ofthe following iscorrect fortheabove conditions?
A. Manually withdraw the TIPdetector and close theBall Valve IAWSO7F.7.A-2 "TIP System Isolation inEvent ofContainment Isolation" B. Manually fire the shear valve IAWSO7F.7.A-2 "TIP System Isolation inEvent of Containment Isolation" C. Manually withdraw the TIPdetector andclose the ball valve IAWCOLGP-8F, "Groups IV, andIV-B Isolation D. Manually fire theshear valve IAWCOLGP-8.F, "Groups IV and IV-BIsolation" Answer: A Answer ExplatigiitionCTWAETWAf Choice BasisorJustification Correct:A ForaTIPfailure toisolate, a COLdirects manual isolation IAW SO 7F.7.A-2, which directs manually withdrawing theTIPdetector toshield and closing theball valve.
SO7F.7.A-2 liststhe order totake the actions toattempt towithdrawbefore firing the shear valve.
Distractors: B Theshear valve isonly fired if thedetector cannotberetracted andthen only if directed bytheShift Manager. Plausible if thecandidate does not understand the requirements following anisolation signal.
C Plausible asa COLwill direct verifying theBall Valve closedandthen manual isolation with SO7F.7.A withthedetector inthecoretheBall Valve notclosed. However that checklistisGP-8.B "Groups andIII II Isolation" andthecandidate mayconfuse theGroup Isolation thatTIPs belongs to.
D Theshear valve isonly fired if thedetector cannotberetracted andthen only if directed bythe Shift Manager. Plausible the if candidate does not understand therequirements following anisolation signal.
Plausible asa COLwill direct the verifying BallValve closedandthen manual isolation with SO7F.7.A withthe detector inthecoretheBall Valve notclosed. However that checklistisGP-8.B "Groups II andIll Isolation" andthe candidate ma confuse the GrouIsolation thatTIPs belon sto.
Page: 53of77 16March 2020
@ @ bl*
tx 2020NRCSROExamrevo TestID: 332227 VlP T QuestionW/Info Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoCom lete: 0 Difficult: 0.00 S stemID: 2132844 User-Defined ID:
Cross Reference Number: 215001 2.1.23 To ic: ILT-5007F-7d-002-SRO CCERT NumField 1: C CERT NumField 2:
Text Field:
Page: 54of77 16March 2020
l :
2020NRCSROExamrev0 Test ID: 332227 Comments: f':
Wf5/7277A?""991"ffP'WfffolW
// Level of Ps chometrics Difficult Time RO Knowledge y Allowance minutes HIGH 10CRF55.43(b)(
5 Source Documentation Source: New Exam item Previous 2 NRC Exam Modified Bank Other ExamBank X ILT Exam Bank (639656)
Reference s : GP-8.B, SO7F.7.A-2, GP-8.F Learning PLOT-5007F-7d Ob'ective:
K/ASystem: 215001 Traversing Importance:
In-Core Probe SRO 4.4 K/AStatement: 2.1.23 -
Ability toperform specific system andintegrated plant procedures during all modes of lant o eration.
REQUIRED None MATERIALS:
Notes and None Comments:
Page: 55of77 16March 2020
[
2020 NRCSROExamrev0 Test ID: 332227 ldD?bMWD2dWfff/fd@dWMD/ddifff///fdbEWf@
Unit2isat100% Power whenthefollowing occurs:
= A leakintheDrywell has resulted in rising Drywell temperature andpressure.
a Allplant systems responded asdesignedasDrywell pressureexceeded 2 psig.
= T-101"RPVControl" and T-102 "Primary Containment Control" havebeenentered
= Adequate Core Cooling is currently being maintained byFeedwater a Therehasbeennorise inMain Stack radiationmonitors
= Whenattempting tospray theDrywell inaccordance with T-204 ofContainment "Initiation Sprays UsingRHR"the following valves did not open a MO-2-10-031A "D/WSpray Inboard" e MO-2-10-026B "D/WSpray Outboard"
= DrywellPressure iscurrently 6 psig andrising slowly Undertheseconditions what would the CRSdirectnext?
A. RRC44A.1-2 "Maximize Drywell Cooling" B. T-223 "Drywell Cooler FanBypass" C. T-205 "InitiationofContainment Sprays Using HPSW" D. T-200 "Primary Containment Venting" Answer: B WE A A 1! N C ME Answer Explanation '
C ".." . . ... .
Choice BasisorJustification Correct:B With Containment Sprays unabletospray intotheDrywelltoreduce pressure andtemperature, DWventilation re-starting isthepreferred option. Since Drywell pressure hasexceeded 2 psigtheDWfans are tripped. This trip mustbebypassed inorder toplace DWventilation back inservice. T-223 provides thedirection tobypass the andplace trip DW ventilation back inservice Distractors: A Plausible asmaximizing DrywellVentilationisa responsetorising drywell temperature andpressure, howeversince theDrywell Ventilation trips at2 psig inthe Drywell, the tripsignalneeds tobebypassed inorder torestart ventilation. TheRa idResonse Card 44Adoes notrovide that direction.
C Plausible asT-205 isanother waytospray containmenttobring down Pressure andTemperature, however T-205 uses thesamevalves that failed too enwhenattemtinT-204.
D Plausible asventing containment isanother waytocontrol Pressure in T-102, however venting containment isacheck /re-checkstatment and should beperformed torestore andmaintain ACCortoreduce total offsite radiation dose. Asstated inthestem ACCismaintained andthere isno rise inoffsite dose. This would notbe erformed atthis time Page: 56of77 16March 2020
2020NRCSROExamrevo Test ID: 332227 Question18AinfoE LLL227;AN A EAAmi3 . Ln ... ... ... .
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stemID: 2130186 User-Defined ID: PLOT-5040C-10A Cross Reference Number: 288000 A2.03 To ic: SRO DW ventilation LOCAandS rasunavailable durin NumField 1:
NumField 2:
Text Field:
Page: 57of77 16March 2020
/
2020NRCSROExamrevo Test ID:332227 Comments: WMffff////AGETWT'=~'"'WTW((($
/
Level of Difficu
/ Time Pschometrics SRO Knowle Ity Allowa dge nce (minute s
HIGH 10CRF55.43 b5 Source Documentation Source: X New Exam itemPrevious NRCExam Modified Bank ExamBank Other ILTExam Bank Reference s : T-102, T-204, T-205, T-223,RRC44A.1 Learning PLOT 5040C-10A -
Ob'ective:
K/ASystem: 288000 Importance;-
SRO Plant 3.7 Ventilation S stems K/A A2.03Ability Statement:thefollowing (a) to predict theimpacts of onthePLANTVENTILATION SYSTEMS ;and(b) basedonthose predictions, useprocedures tocorrect, control, ormitigate theconsequences of those abnormal conditions oroperations:
Loss ofcoolant accident REQ UIRED None MATERIALS:
Notes and This question meets therequirementsof Comments: 10CFR55.43(b)5 because theSROmust evaluate plantconditionsandthen makea decision onwhat to erform next.
Page:58of77 16March2020
n-,,,,wn==
2020NRCSROExamrev0 Test ID: 332227 40N@W@i@F/2$$$$hbi99$iffff/$jfM/ki$fffffffffffifA$[WfMAh PerOP-AB-300-1003, "BWR Reactivity Maneuver Guidance", a Reactivity Maneuver Approval (ReMA)
Package isrequired for which ofthe following activities?
A. Inserting control rods toclear APRMHialarms.
B. Adjusting reactor recirculation flowtomaintain full reactor power.
C. Unplanned insertion of acontrol rod for operability concerns.
D. Withdrawing control rods during continuation ofa reactor startupabove 25%power.
Answer: D Answer Explanations A ww A n n Pn exmn C Choice Basis or Justification Correct:D Correct -
PerOP-AB-300-1003, "BWR Reactivity Maneuver Guidance" continuation ofa reactor startu isacom lexmaneuver andreuires a ReMA.
Distracto A Plausible asthis isa reactivity Maneuver and is covered byOP-AB-300-1003, rs: however inserting control rods toclear APRM Hialarm is considered a simple reactivit maneuver erOP-AB-300-1003 and a ReMA is notreuired.
B Plausible asthis isa reactivity Maneuver andiscovered byOP-AB-300-1003 however routine load changes with reactor recirculation flow is considered a simlereactivit maneuver erOP-AB-300-1003 anda ReMA is notreuired.
C Plausible asthis isa reactivity Maneuver andiscoveredby OP-AB-300-1003, however unplanned insertion ofacontrol rod for operabilityconcerns is a simlereactivi maneuver erOP-AB-300-1003 anda ReMA is not reuired.
Page: 59of77 16March 2020
b; ! f 2020NRCSROExamrev0 Test ID: 332227 Question 19InfoAAAm Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 2 Difficul : 2.50 S stemID: 994298 User-Defined ID: ILT-1535-4-001 Cross Reference Number: 2.1.37 Topic: ILT-1535-4-001 A Reactivity Maneuver (ReMA) Formis re uired for which ofthe followin activities NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Difficulty Time SRO Knowledge Allowance minutes Memory 10CRF55.43(b) 6 Source Documentation Source: NewExamitem Previous NRCExam Modified Bank Other Exam Bank X ILT ExamBank Reference(s): OP-AB-300-1003, BWRReactivity Maneuver Guidance, GP-5 Learning PLOT 1535-4 -
Ob'ective:
K/ASystem: Importance; RO/SRO 4.6 K/A 2.1.37 -
Knowledge ofprocedures, Statement: guidelines, orlimitations associated with reactivit manaement.
REQUIRED None MATERIALS:
Notes and This question meets therequirements of Comments: 10CFR55.43 because theSROis responsible toapprove theReMApackage before power changes meeting the reuirements ofOP-AB-300-1003 Page:60of77 16March2020
2020NRCSROExamrevo TestID: 332227 Dff[ff[$271(ffA7A)>3957A'/////31/r7fffffNMMW///ff#A$22MMAN/A1i!
Youarethe Unit2 control roomsupervisor E1Diesel GeneratorSupplemental Supply fan requiringminor maintenance torepair acracked support piece, isawaitingyour approval a This Maintenance requires placing the E1Diesel Generator inPull toLock a Current outside temperature is50 F An Equipment Operator reportsthe following:
a StartingAirReservoir (Automatic Start) for theE3Diesel Generator isreading 0 psig, a StartingAirReservoir (Manual Start) for the E3Diesel Generator isreading 260psig.
Which oneofthe following describes theactions of the control room supervisor:
1)Declare E3Diesel Generator OPERABLE orINOPERABLE AND 2)DoyouAPPROVE orNDIAPPROVE Maintenance onthe E1 Diesel Generator Supply Supplemental fan A. 1) OPERABLE
- 2) APPROVE B. 1)INOPERABLE 2)APPROVE C. 1) OPERABLE
- 2) NOIAPPROVE D. 1)INOPERABLE
- 2) NDIAPPROVE Answer: D Page:61of77 16March 2020
h 2020NRCSROExamrevo Test ID: 332227 Choice Basis orJustification Correct: D Since the Automatic Starting Air is0psig, the E3Diesel Generator will not Automatically start from astandby ona Loss ofPower Condition. This makes the Diesel Generator INOPERABLE. Themaintenance would notbeapproved at this time because although maintenance isrequired atthistime theE1 Diesel Generator isconsidered operable. Whenthe E1Diesel Generator is placed in Pull toLock the E1Diesel Generator would thenbeconsidered INOPERABLE andwould putboth Units inaTech Spec for2 INOPERABLE diesels.
DistractoA First part isplausible astheManual Starting air ispressurized andtheDiesel rs: could bestarted with theManualStarting air. This makes the diesel available, however itisstillINOPERABLE and the c andidate maymisapplytwo the terms.
Second part isplausible since the maintenance isrequired ontheE1Diesel Supplemental Supply Fanwhich is only required tobeoperable if outside air temperature is> 80 F,however since this maintenance requires the E1Diesel Generator tobeplaced inPull to Lock, the E1Diesel Generator would be considered INOPERABLE andthe maintenance would notbeapproved atthis time.
B First Part iscorrect Second part isplausible since the maintenance isrequired onthe E1Diesel Supplemental Supply Fanwhich isonly required tobeoperable if outside air temperature is> 80 F,however since this maintenance requires the E1Diesel Generator tobeplaced inPull toLock, theE1Diesel Generator would be considered INOPERABLE andthe maintenance would not beapproved at this time.
C First part isplausible astheManual Starting air ispressurized and theDiesel could bestarted with theManual Starting air. This makes the diesel available, however itisstillINOPERABLE andthe candidate maymisapply the two terms.
Second Part iscorrect Page:62of77 16March 2020
2020 NRCSROExamrev0 TestID: 332227 Question 201nfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoCom lete: 3 Difficult: 3.00 S stemID: 2130151 User-Defined ID: PLOT-DBIG-1529 Cross Reference Number: 2.2.21 To ic: PLOT-1529 -
A rove testinwhile INOP Diesel NumField 1:
NumField 2:
Text Field:
Page:63of77 16March 2020
2020NRCSROExamrev0 Test ID:332227 Comments: W7///////f//f*
[(RWT""*'""tArag"':'i None Level of
//
Difficult Psychometrics Time SRO Knowled y Allowan ge ce (minutes HIGH 10CFR55.43(b) 2 Source Documentation Source: X New Exam item Previous NRCExam ModifiedBank Other ExamBank ILTExamBank Reference s : OP-AA-108-104, TS 3.8.1 and3.8.3, TS3.0 Learning PLOT 15291k -
Ob'ective:
K/ASystem: importance; RO / SRO 4.1 K/A 2.2.21 -
Knowledge ofpre- and Statement: ost-maintenance o erabilit reuirements.
REQUIRED None MATERIALS:
Notes and This meetstherequirements oftheK/Aas Comments: the candidate mustevaluate a situation that involves theaddressing ofsystem operability inconjunction withapproval of maintenance testin .
Page:64of77 16March 2020
me n 2020NRCSROExamrev0 Test ID: 332227 4AE5N@2[f((f!///////////////fffff)fWMffff) RMW)ffff//W3WM Unit 2 isat100% power Thefollowing alarms are received:
a 003D-2"Main Stack Radiation High" a 003D-1"Main Stack Radiation High-High" Nootheralarmsorchanges inplant status occur TheROobtains the following readings:
a RI-0-17-050Aisreading 6.24E05 uCi/sec e RI-0-17-050Bisreading 3.56E01 uCi/sec Whichoneofthe following istherequired actionregarding these indications?
A. Place 17A-S8 "High RadTrip Inbd Isol Byp" switch toBYPASSDNLY B. Enter T-104 "Radioactivity Release" ANDPlace17A-S8 "High RadTrip Inbd Byp" Isol switch toBYPASS C. Perform AO63E.1-2 "Bypassing a Failed Main Stack Radiation Monitor Channel To Prevent Masking Operable Main Stack Radiation ChannelAnnunciators" QNLY D. Place 17A-S8 "High RadTrip Inbd Isol Byp" switch toBYPASS AND Perform AO63E.1-2 "Bypassing a Failed Main Stack Radiation Monitor Channel To Prevent Masking Operable Main Stack Radiation Channel Annunciators" Answer: C ExplanationL P$hmdfMAdf12221% Af ;k Answer Choice Basis orJustification Correct:C Actions outofARC003D-2saytoperform AO63E.1-2 ifonlyonechannel is indicating high andthat indication hasbeen determined asnotreal. The'A' channel ofmainstack radmonitor isreading highandwith noother changes in lant status oralarms canbeconsidered a false readin Distractor A Plausible asthecandidate maymisapply the fact that theradmonitor is s: malfunctioning andbypass itsisolation capability. Performing thiswouldalso maskfurther alarms fortheo erable Main Stack Radiation Monitor.
B Plausible ifthecandidate misinterprets indications givenasafailed instrument andenter T-104 onMainStack Radabove theHIHIAlarm Setpoint outofthe ARCandthen bypass the monitortoclear the alarmand exit T-104.
D Plausible asthe candidate maymisapply the fact that the radmonitor is malfunctioning andbypass itsisolation capability. Performing thiswouldalso maskfurther alarms forthe operable Main Stack Radiation Monitor.
Performin AO63E.1-2 would betheroerresonse.
Page:65of77 16March 2020
on Te m==re n
- n 2020NRCSROExamrev0 Test ID
- 332227 QuestionErinfo Question T e
- Multi leChoice Status
- Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 3 Difficul : 2.00 S stemID: 2130409 User-Defined ID:
Cross Reference Number: 2.3.5 To ic: PLOT-5063C-9-002 Failed MainStack Radmonitor NumField 1:
NumField 2:
Text Field:
Comments:
Ps chometrics Level of Diffic Time RO Knowle ulty Allowa dge nce (minut es HIGH 10CRF55.43 b5 Source Documentation Source:X NewExamitem Previous NRCExam Modified Bank OtherExam Bank ILTExamBank RefereARC-003 D-1, ARC-003 D-2, ARC-003 D-3 nces :
Learnin PLOT-5063C-9 9
Objecti ve:
K/A 2.3Radiation Importance:
SystemControl RO/SRO
~ 2.9 K/A 2.3.5-Abilitytouseradiation monitoringsystems, Statemsuchasfixed radiation monitors andalarms, ent: portable survey instruments, personnelmonitoring e uiment, etc.
REQUI None RED MATER IALS:
Notes This meets theK/Aasit istheSRO's jobfunction and onwhether tobypass installed equipment.
Comme nts:
Page: 66of77 16March 2020
ij 2020 NRCSROExamrev0 Test ID: 332227 WhW$ifWM$/////W/JSANNA25AWAFAA7//A5//////41117///A27/////40 A General Emergency is declared due toa loss ofthe Reactor CoolantSystem andContainment barriers anda potential lossof the Fuel Cladding Barrier.
= Winddirectionisfrom 280 degrees
= TheTSCisstaffed butcommand andcontrol hasnotbeen transferred
= Doseassessment indicates 1100 mRemTEDEbeyond the boundary site onthe Based above conditions theShift Emergency Director's PARshall initial recommend Evacuate 2 Radius Mile AND A. Evacuate 2 10miles insectors LMNPQ B. Evacuate 2 5 miles insectors LMNPQ C. Evacuate 2 10miles insectors CDEFG D. Evacuate 2 5 miles insectors CDEFG Answer: C Answer ExplandipoE A 1 C AL A Choice BasisorJustification Correct: C Using thePARflowchart inEP-AA-111-F-08,weareled toEvacuate 2 10miles.
This isbecause theevent a Rapidly constitutes Progressing Severe Accident astheconditions havebeenmet foran EALRG1(>1000 mRemTEDEbeyond boundary) site Thewind direction isfrom 280degrees andusing Table1sectors CDEFG should beevacuated.
Distracters: B Plausible ifEP-AA-111-F-08 ismisappliedanditisbelieved the Rapidly Progressing Severe Accident thresholdhasnotbeenmet.
This leads the flowcharttoevacuate 2 5 miles.
Plausible if table is misapplied asthe sectors listed are180degrees opposite and considered upwind.
D Plausible ifEP-AA-111-F-08 ismisappliedanditisbelieved the Rapidly Progressing Severe Accident thresholdhasnotbeenmet.
This leads the flowcharttoevacuate 2 5miles.
Thedownwind sectors arecorrect A Evacuating 2 10miles iscorrect.
Plausible iftable ismisapplied asthesectors are180degrees listed opposite andconsidered upwind.
Page: 67of77 16March 2020
- : n+ . . == .. ... n c
2020NRCSROExamrev0 Test ID: 332227 Question 22Ntfoi Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficult: 0.00 S stem ID: 2096147 User-Defined ID:
Cross Reference Number: 2.4.44 To ic: ILT G5-6-003 SRO PARrecommendation NumField 1:
NumField 2:
Text Field:
Comments: Psychometrics Level of Difficulty Time Allowance SRO Knowledge (minutes)
High 10CFR55.43(b)
(4)
Source Documentation Source: NewExamitem Previous NRC Exam X Modified Bank (2115519) Other Exam Bank ILT ExamBank Reference(s): EP-AA-111-F-08 Learning G5-6 Objective:
K/A System: G2.4 Emergency -
Plan importance; SRO 4.4 K/A 2.4.44Knowledge ofemergency plan Statement:protective action recommendations.
REQUIRED EP-AA-111-F-08, EP-AA1007 Addendum 3 (pg 2-1 MATERIALS:ONLY)
Notes and Comments:
Page: 68of77 16March 2020
2020NRCSROExamrevo Test ID:332227
,g; g iBW E ' $8$4A;ift $ff$fg$AW$j $$$l$$$it "M$$$Agga Q$WAgfflifi ffphig A Unit 2isat100%power whena primary system breach occurs following:
inthe resulting a Annunciator 003D-2"MAIN STACK RADIATION HIGH" alarming
= Annunciator 003D-1"MAIN STACK RADIATION HIGH-HIGH" alarming a RI-0-17-050A/B main stack radiation recorderreads 2.1E+6uCi/sec andrising a RI-0-17-050A/B main stack radiation recorder Tateofase is1.0E+6uCi/secper minute a Calculated offsite dose rate is0.58 mRem/hr TEDE a Activities are ongoing toidentify and isolate the leak REDUCE THERADRELEASE TOBELOW THE T-104ENTRYCONDITIONS ANDMAINTAIN IT ASLOWASPOSSiBLE BYPERFORMING THE FOLLOWING AS APPROPRIATE:.
- REACTOR POWER REDUCTION (GP-5ORGP-9)
- REMOVE EQUtPMENT FROM SERVICE EXCEPT SYSTEMS REQUIRED TOBEOPERATED INTHE TRFPPROCEDURES
- PLACEALTERNATE TRAN OREQU1PMENT INSERVICE
- OTHERACTION ASDETERMANED BYSHIFT MANAGEMENT L- RR4 g
I BEFORE THERADRELEASE REACHES THEALERT LEVEL, PERFORM THEFOLLOWING ONTHEOFFENDiMG UNIT:
1.MANUALLY SCRAMTHEREACTOR USINGGP-4 2.ENTERT401ANDEXECUTE 1T CONCURRENTLY WITHTHIS PROCEDURE 3.UNLESS DIRECTED OTHERWISE, PERFORM RPVDEPRESSURizATION PER =
APPLICABLETRIPPROCEDURE T4M L RR-9 #
g I
BEFORETHERAORELEASE REACHES THERATE REQUIRING A GENERAL EMERGENCY AND f Ah ISDISCHARGING OUTSIDE PRfMARYANDSECONDARY CONTAINMENTS, PERFORM ANEMERGENCY BLOWDOWN ON THEOFFENDING UNITUSINGT412 at 88 T-112 L L- RR-10 69of77 Page: 2020 16March
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.. ... .. ...... nn T""" "' ' -
T"' "
1P" "
2020NRCSROExamrev0 Test ID: 332227 ofthe Which following istheTequitedaction inaccordance with T-104 "Radioactivity Release"?
A. GP-9-2 "Fast Reactor Power Reduction" B. GP-4"Manual ReactorScram" with depressurization < 100F/HR C. GP-4"Manual Reactor Scram" with rapid depressurizing regardless ofcooldown rates using bypassvalves D. T-112 "Emergency Blowdown" Answer: A Answer ExpMnationkmA xn... CL........ CCC................... ..... .
Choice Basis orJustification Correct: A This iscorrect asthe readings for the radiation recorder arestillafactor of10 away from the ALERTLevel. With the rising rate there issufficient time to attem t ower reduction before erformin a manualscram.
Distracto B Plausible because this would becorrect ifthe radiation reading werecloser to rs: the ALERTlevel orthe rate ofrise weremore aggressive. Given thecurrent rate ofrise there ismorethan 50minutes before anALERTwould bereached allowing ample time toperform a power reduction. Placing the plant ina transient byperforming a SCRAM that maybeavoided byother measures is not a conservative decision.
C Plausible asthis would becorrect if the radiation reading were much higher (approaching a General emergency) andrapidly rising. In this case the CRS would direct theGP-4 andbegin a rapid depressurization using bypass valves before roceedin toanEmerenc Blowdown ifnecessa D Plausible asthis would becorrect if radiation wasapproaching a General Emergency level andtherate ofrise would not allow rapid depressurization before erformin anEmerencBlowdown Page: 70of77 16March 2020
6 7, 4 2020NRCSROExamrev0 Test ID: 332227
.Questiohl231nfoAAC Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 3 Difficult
- 2.00 . .. . ..
S stemID: 993749 User-DefinedID: ILT-2104-1-001 Cross Reference Number: G 2.3.11 To ic: SRO ILT-PBIG2104 Re uired action for Hihrad NumField 1:
NumField 2:
Text Field:
Comments: Psychometrics Level of Difficulty Time SRO Knowledge Allowance (minutes)
HIGH 10CRF55.43(b)5 Source Documentation Source: NewExamitem PreviousNRC Exam Modified Bank Other ExamBank X ILT ExamBank Reference(s): T-104 andbases, EP-AA-1007 addendum 3 Learning PLOT2104 -
Objective:
K/A System: Importance;RO/SRO 4.3 K/A Statement: 2.3.11 -
Abilitytocontrol Radiation Releases REQUIRED EP-AA-1007 Addendum 3 (pg2.1ONLY)
MATERIALS:
Notes and This question meets10CFR43b criteria Comments: because thecandidate mustusethechart tomakeadetermination oftheir place within thetrip procedure andthenext action totake.
Page: 71of77 2020 16March
. ............. .. :n: : .. . = . ::-
2020NRCSROExamrev0 Test ID: 332227
@65b%Wflff////7ff5M/////////72//J7NMME557affffifff/AfffAEfff2 BothUnits operating at100%
are power with the following:
The4KVsystem isina normal line-upwith thefollowing exceptions:
a E-312 breaker isracked out forelevator mechanism preventative maintenance.
a E-233 breaker isracked out foremergent maintenance 10minutes later:
E-322 breaker spuriouslytripsopen AII other plant equipment operates asdesigned Basedontheseconditions, the following LCO('s)will beentered:
A. Unit 2 Potential LCO3.8.1 condition'A' -
One Offsite circuit inoperable Unit 3 Potential LCO3.8.1 condition 'A' -
One Offsite circuit inoperable B. Unit 2 LCO3.8.1 condition 'A'OneOffsitecircuit inoperable Unit 3 Potential LCO3.8.1 condition 'A'OneOffsite circuit inoperable C. Unit 2 Potential LCO3.8.1 condition 'A'OneOffsite circuit inoperable Unit 3 LCO3.8.1 condition 'A'OneOffsite circuit inoperable D. Unit 2 LCO3.8.1 condition 'A'OneOffsite circuit inoperable Unit 3 LCO3.8.1 condition 'A'OneOffsite circuit inoperable Answer: B Page: 72of77 16March 2020
CWmjjan::ese:e= =VL=:=
i; 2020NRCSROExamrevo Test ID: 332227 Choice Basis orJustification Correct: B En Unit 2 LCO3.8.1 would beentered with oftheE-322 thetrip breaker. Both the E-312 Breaker andE-322 breakerarefed from the 3 SUEoff-site source. With both breakersopen the3 SUEoff-site circuit inINOPERABLE forUnit 2since it isunabletoprovidepower to3outof4 4kVbuses.
OnUnit 3there isa potential for LCO3.8.1 asE-233isracked out.
This has limitedthe 2 SUEstartup sourceto3outof4 kVbuses and a potential would beentered because anotherfailure would cause entry intothat LCO.
Distracters: A Plausible asboth Units areina potential LCOandcould enter another Potential. Depending onthe next another failure, potential maybeentered ona Unit. If 212, 222,232,or242weretotrip open there wouldbe another potential Unit 2.
Second part iscorrect.
C Plausible if thecandidate misinterprets what anoffsite constitutes circuit onwhich unit. If 212, 222, 232, or242were open totrip there would beanother potential Unit 2.
Plausible asthecandidate may misapply theoffsite of3 SUE circuit beinrelated totheUnit 34kv systemThis isacommon error.
D Firstpart iscorrect Plausible asthe candidate maymisapply the of3 SUE circuit offsite being related tothe Unit 34kvsystem. This isacommon error.
Page: 73of77 16March 2020
- . x
.. .. wme: mm .
m::::: m
=
2020NRCSROExamrev0 Test ID: 332227 CE Question##iifo!
Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 Time toComlete: 0 Difficul : 0.00 S stemID: 2130408 User-Defined ID:
Cross Reference Number: 2.2.36 To ic: SRO off-site circuit TSent NumField 1:
NumField 2:
Text Field:
Comments: Psychometrics Level of Difficulty TimeAllowance RO Knowledge (minutes)
HIGH 10CFR55.43(b)
(2)
Source Documentation Source: X NewExamitem Previous NRCExam Modified Bank Other Exam Bank ILT ExamBank Reference(s): PLOT-5054; SO52A.1.B; Tech Spec3.8.7, Tech Spec 3.8.1 Learning PLOT-5054 13 Objective:
K/A System: importance; SRO 4.2 K/A 2.2.36 -
Abilitytoanalyze theeffect of Statement:maintenance activities,suchasdegraded power sources, onthe status oflimiting conditions for operations.
REQUIREDNONE MATERIALS:
Notes and Comments:
Page: 74of77 16March2020
2020NRCSROExamrevo Test ID: 332227
$$ddf$f$/J//fffjij//fiff/NMj/////)?/N/ ///fd$fhWdt Unit 2isat85%power during endofcycle coast down.
Newfuel isbeingmoved inthe fuel pool inpreparations forthe upcoming outage a TheReactor ServicesSupervisor reports that Fuel pool hasunexpectedly level to232ft lowered 2 in TheCRSmust (11 10minutes later a Fuel pool level is12.5 ftonLl-2-19-001A.
TheCRSmust (2) .
CURVE FP/L-5 FUELPOOLLEVEL VERSUS PLANTELEVATION a .
d ul E
8225 5
B at 22o
!E 215 j 210 ~ ~ ' - ' ~
0 is 5 7.5 10 115 15 17.5 20 22.5 FUELPOOLLEVEL ONU-2(3)-19-001A(B)
A. (1) enter ON-124 "Fuel Floor andFuel Handling ONLY Problems" (2) makeup t the o f uelpool (only)
B. (1) enter ON-124 "Fuel Floor andFuel Handling DNLY Problems" (2) makeup tothe fuel pool andspray thefuelpool C. (1) enter ON-124 "Fuel Floor andFuel Handling ANDT-103 Problems" "Secondary Containment Control" (2) makeup tothe fuel pool (only)
D. (1) enter ON-124 "Fuel Floor andFuel Handling ANDT-103 Problems" "Secondary Containment Control" (2) makeup tothe fuel pool andspray thefuelpool Answer: C Page: 75of77 16March 2020
mx me m m ii 2020NRCSROExamrev0 Test ID:
332227 Answer Exlanation . . . .. .... ... . . . . . .... ... . . ... . .... .
Choice Basis orJustification Correct: C ON-124 isentered astheFuel poollevel hasdropped unexpectedly. T-103 would beentered ona lowFuel Pool level of232Ft4 inches. FuelPool level at12.5 ftasindicated on Ll-2-19-001A isabout 10feet below normal level and requires the fuelpool toberestored andmaintained byusing fuel ool makeu sources.
Distractors A Plausible if thecandidate believes that conditions require entry ON-124 into only forthe unexpected drop i fuel n pool level, however T-103would also beentered when theFuel Pool Cooling Trouble alarm comesinona low Fuel Pool level of 232 Ft 4 inches.
Second art iscorrect B Plausible ifthe candidate believes that conditions require entry ON-124 into only fortheunexpected drop infuel pool level, however T-103would also beentered whentheFuel Pool Cooling Trouble alarm comesinonalow Fuel Pool level of232Ft4 inches.
Plausible astheFuel Pool level has lowered substantially andFuel Pool Sprays are awaytocombat lowering Fuel Pool Level, however sprays are not required tobelined upuntil Fuel Pool levelcannot bemaintained above 220Feet elevation. With Ll-2-19-001A indicating 12.5ft weareat a roximatel 223Feet elevation.
D First partiscorrect Plausible astheFuel Poollevel haslowered substantially andFuel Pool Sprays areawaytocombat lowering FuelPool Level, however sprays are not required tobelined upuntil Fuel Pool level cannot be maintained above 220Feet elevation. With LI-2-19-001A indicating 12.5ft we areat a roximatel 223Feet elevation.
Page: 76of77 16March 2020
=
w 2020 NRCSROExamrev0 Test ID: 332227 Question251nfo Question T e: Multi leChoice Status: Active Alwasselect on test? No Authorized for ractice? No Points: 1.00 TimetoComlete: 0 Difficul : 1.00 S stemID: 2130407 User-Defined ID: ILT-2103-3-002 Cross Reference Number: 2.4.8 Topic: ILT- 2103 3 002SRODescribe howevent-based Emerenc /Abnormal o eratin rocedures areu NumField 1:
NumField 2:
Text Field:
Comments: Psychometrics Levelof Difficulty Time SRO Knowledge Allowance (minutes)
High 10CRF55.43(b)5 Source Documentation Source: NewExamitemPrevious NRC Exam X Modified Bank (2115498) Other Exam Bank ILT ExamBank Reference(s): ON-124, T-103 andbases Learning PLOT- 21033 Objective:
K/A System: importance;RO/SRO 4.5 K/A 2.4.8 -
Knowledge of howabnormal operating Statement:procedures areused with inconjunction EOPs REQUIRED None MATERIALS:
Notes and Graph is embedded toanswer asitisnecessary Comments: thequestion. Thegraph isused tomake decisions ontheEOP,tobetter match theK/A.
Page: 77of77 16March2020