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| {{#Wiki_filter:ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross- | | {{#Wiki_filter:}} |
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| ==Reference:==
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| Level RO Tier # 1 Group # 1 K/A# 295001AK2.07 Importance Rating3.5 Partiai orComplete Loss of Forced Core Flow Circulation Knowledge oftheinterrelations between PARTIAL ORCOMPLETE LOSSOFFORCED COREFLOWClRCULATION and the following: Core flow indication Proposed Question: #1 Theplant isoperatingat100%power when the following occur:
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| Time (minutes) Condition(s) 0 . RWRMGSet A Field Breaker trips.
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| . AOP-8, Unexpected Change inCore Flow, isentered.
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| 10 . A Reactor Operator reports that therequired 5 minute wait period in AOP-8hasjust commenced.
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| Which oneofthe following describes thestatus offlow inRecirculation loopA and indicated core flow atpanel 09-5 attime11minutes?
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| =
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| M Indicated CoreFlow atPanel 09-5 A. ThereisNOflow isaccurate B. There isNOflow IsNOTaccurate C. Reverse flow ispresent Isaccurate D. Reverse flow ispresent isNOTaccurate
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| Proposed Answer: A Explanation: Given thatthe5 minute wait period inAOP-8 hascommenced, thedischarge valve for Recirculation pumpA hasbeenfully closed andnotyet open.
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| throttled Therefore, there isnoflow inRecirculation loop A.Indicated core flow isaccurateunder these conditions.
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| B. Incorrect -
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| Indicated core flowisaccurate under these conditions. Plausible becauseatthis point inAOP-8,numerous required actions affectingtheRecirculation systemhavenotbeen taken, such asplacing theTLO/SLO toggle switch inSLO.
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| C. Incorrect -
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| There iscurrently noreverse flow inRecirculation loop because A.Plausible there wasbefore theReactor Operator closed the associated discharge valveandtherewill beagain following the5 minute waitperiod whenthe discharge valve isthrottled backopen.
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| D. Incorrect -
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| There iscurrently no reverse flow inRecirculation loopA.Plausible because there wasbefore theReactor Operator closedthe associated discharge valveandtherewill beagain following the5 minute wait period when the discharge valve isthrottled backopen.
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| Indicated core flow isaccurate under these conditions. Plausible because atthispoint in AOP-8, numerous required actions affecting theRecirculation system havenotbeentaken, such asplacing the TLO/SLO toggle switch in SLO.
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| Technical Reference(s): AOP-8, SDLP-02H Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-02H 1.09.e Question Source: Modified Bank3/12-NRC#1 Question History:
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| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(7)
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| Comments:
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| AK 2.01 Knowledge oftheinerrelations between PARTIAL ORCOMPLETE LOSSOF FORCED COREFLOWCIRCULATION andthefollowing: (CFR: 41.7 I45.8)
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| Recirculation syshm Proposed Question: 1 Theplant is operating at100% reactor power whenthe following occurs
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| * Time = 00 min: 'A' RWRMGSetField Breaker trips andAOP-8, Loss orReduction ofReactor Coolant Flow, isentered
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| * Time= 10min:The Reactor Operator reportsthat the required 5minute wait period for theidle RWRicop has commenced and that loop temperature isfowering2*Flhr.
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| AtTime = 11min, the Operator whoismonitoring core total flow would expect tosee indicated flow tobe (1)actual flow because thereverse flow summer (2) .
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| X !the'saine iis 'senses no'DP B ?the same as senses anegative DPandTs sulitractTng the flow C leiis thari
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| 'senses apositive DPandTs sufifractTng~the flow Pro Posed Answer:
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| KPIfieCsiiififf "seriii.Eis'no DP IAFMarch 2CC 2 NRCExam
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| ES-401 Written Examination Question Worksheet FormES4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
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| Level RO Tier# 1 Group # 1 K/A# 295003 AA2.02 importance Rating4.2 Partial orCompleteLoss ofACPower Ability todetermine and/or interpret thefollowing asthey apply toPARTIAL OR COMPLETE LOSSOFA.C.POWER: Reactor power /pressure /andlevel Proposed Question: #2 A startup isinprogress with the following:
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| * TheReactor isatthe point ofaddingheat (POAH).
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| * Reactor pressure is0 psig.
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| Then, a Station Blackout occurs. TheUPSinverter fails to transfer toDC.
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| Which oneofthe following identifies indications that canbeused todetermine Reactor power andwater level under these conditions?
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| Reactor Power Reactor Water Level A. IRMDownscale lights onPanel 09-5 Fuel zone level indicator 02-3Ll-92 onPanel 09-4 B. IRMDownscale lights onPanel 09-5 WideRange level recorder 06LR-97 onPanel 09-5 C. IRM/APRMrecorder onPanel 09-5 Fuel zone level indicator 02-3LI-92 onPanel 09-4 D. IRM/APRMrecorder onPanel 09-5 WideRange level recorder 06LR-97 onPanel 09-5
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| Proposed Answer: A Explanation: With theloss ofall ACpower andfailure oftheUPStotransfer toDC,IRMand APRMrecorders areunavailable,butIRMDownscale are lights functional.
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| still Also,Wide Range level recorder is unavailable,but Fuel zone level indicator 02-3Ll-92onPanel 09-4 is available.
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| h A psychometrically soundquestion wasonly able tobedeveloped toaddresstwoofthe three parameters mentioned inthe sub-K/A. Theplant conditionsusedinthequestionwere selected such thatonlytwo ofthe three parameters would beofconcern, based onthis question construction limitation.
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| B. Incorrect -
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| WideRange level recorder is unavailable. Plausible becauseotherlevel indications remain available.Also plausible that Fuel zone levelindicator would bepowered from UPS.
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| C.incorrect -
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| IRMandAPRMrecorders are unavailable. Plausible becauseotherpower indications remain available. Also plausible thatIRM/APRM recorders wouldbepowered from UPS.
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| D. Incorrect -
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| IRMandAPRMrecorders areunavailable. Plausiblebecause otherpower indications remain available. Also plausible that IRM/APRM recorderswouldbepowered from UPS.WideRange level recorder isunavailable. Plausible because otherlevel indications remain available. Also plausible that Fuel zone level would indicator bepowered from UPS.
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| Technical Reference(s):AOP-21, AOP-49 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-71E 1.14 Question Source: Bank 17-1 NRC#53 Question History: 17-1 NRC#53 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(7)
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| Comments:
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| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
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| Level RO Tier # 1 Group # 1 K/A # 295004AA2.03 Importance Rating2.8 Partial orCompleteLoss ofDCPower Ability todetermine and/or interpret thefollowing asthey apply toPARTIAL OR COMPLETE LOSSOFD.C.POWER: Batteryvoltage Proposed Question: #3 Theplant isoperating at100%power with the following:
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| * BatteryCharger A isde-energized due to a malfunction.
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| a StationBattery A voltage is130VDCand slowly lowering.
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| * AOP-45, Loss ofDCPower System A,hasbeen entered.
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| Which oneofthe following identifies the threshold for Station Battery A voltage that requires mitigating actionandthe associated concern, inaccordancewith AOP-45 andOP-43A, 125 VDCPower System?
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| Mitigating actionmustbetaken whenStation Battery A voltage reachesthe threshold of..
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| A. 125VDCtoprevent damage toloads duetohigh current.
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| B. 125VDCtoprevent damage tothe battery duetovoltage reversal.
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| C. 105VDCtoprevent damage toloads duetohigh current.
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| D. 105VDCtoprevent damage tothebattery duetovoltage reversal.
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| Proposed Answer: D Explanation: Thesecond override inAOP-45 requires mitigatingaction whenStation A Battery voltagereaches 105VDC.This isbased onmitigating damage duetovoltage tothebattery reversal.
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| A. incorrect -
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| 105 VDC is the threshold. Plausible because 125VDCisthe nominal of rating the battery andmuch lowerthan normal operating voltage. Thereason isdamagetothe battery duetovoltage reversal. Plausible because lowvoltage will also loads cause topull higher currents,which is notdesirable.
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| B. Incorrect -
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| 105VDCisthe threshold. Plausible because 125VDCisthenominal ratingof thebattery andmuchlower than normal operating voltage.
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| C. Incorrect -
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| Thereason isdamage tothe battery duetovoltage reversal.
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| Plausible because lowvoltage will also cause loads to pullhigher currents, which isnotdesirable.
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| Technical Reference(s): AOP-45, OP-43A Proposed references tobeprovided toapplicants during examination: None Learning Objective: LP-AOP 1.03 Question Source: BankNMP12015 Cert #51 Question History:
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| Question CognitiveLevel:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(10)
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| Comments:
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| | |
| ES-401 Written Examination QuestionWorksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
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| Level RO Tier # 1 Group # 1 K/A# 295005 2.4.31 ImportanceRating4.2 Main Turbine Generator Trip Knowledge ofannunciator alarms, indications, orresponse procedures.
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| Proposed Question: #4 Theplant isoperatingat100%powerwith thefollowing:
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| a Thefollowing annunciators alarm:
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| o 09-7-3-08, MAINGENSTATOR WTR SYS TROUBLE o 94-HSC-7, CONDUCTIVITY ABOVE0.45 MICROMHO'S STATOR WATER CONDUCTIVITY HIGH o 94-HSC-8, CONDUCTIVITY ABOVE9.66MICROMHO'S STATOR WATER CONDUCTIVITY HIGH-HIGH a Operators have validated these alarms.
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| Which oneofthe followingdescribes theplant response and/orrequired Operator in response, accordance withthe Alarm Response Procedures?
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| A. Anautomatic Turbine tripoccurs immediately.
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| B. Anautomatic Turbine tripoccurs after a 70second time delay.
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| C. NOautomatic Turbine tripoccurs andNOReactor scram isrequired.
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| D. NOautomatic Turbine tripoccurs. A rapid powerreduction andReactor scram are required.
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| Proposed Answer: D Explanation: Thegiven annunciators indicate thatStator Water conductivity ishigh. With annunciator 94-HSC-8 inalarm, conductivity isabove 9.66 mmho/cm. Thereisnoautomatic Turbine trip on this signal. This requires arapid power reduction. from Starting 100%power, the rapid power reduction will endwith power stillabove 25%.Therefore, aReactor scramwill also then berequired, which will lead totripping ofthe Main Turbine aspartofthescram response.
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| A. Incorrect -
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| There isno automatic Turbine trip onthis signal. Plausible because otherStator Water Cooling alarms are associated withautomatic Turbine trips anda manual Reactor scram (with ensuing Turbine trip) is required.
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| B.incorrect -
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| There isnoautomatic Turbine trip onthis signal. Plausiblebecause otherStator Water Cooling alarms are associated withautomaticTurbine trips anda manual Reactor scram (with ensuing Turbine trip)is required. Also plausiblebecause thereisa 70second time delay associated with Turbine trips coming from StatorWater Coolingsignals.
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| C.Incorrect -A Reactor scram isrequired. Plausible because this wouldbecorrect if initial Reactor werelower power if or 94-HSC-8was not alarm. in Technical Reference(s): 09-7-3-8, 94-HSC-7, 94-HSC-8 Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: SDLP-94E 1.15 Question Source: New Question History:
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| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(10)
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| Comments:
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| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
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| Level RO Tier # 1 Group # 1 K/A# 295006 AK3.06 importance Rating3.2 Scram Knowledge ofthe reasonsfor thefollowing responses asthey applytoSCRAM:
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| Recirculation pumpspeed reduction: PlantSpecific Proposed Question: #5 Theplant isoperating at80%power withthe following:
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| a A smallsteam leak develops inthe Drywell.
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| TheReactor ismanually scrammed inaccordance with AOP-1, Reactor Scram.
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| a Reactor water level reaches alow of140" before recovering tothenormal band and being stabilized at200" using Feedwater.
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| Which oneofthe following describes the resulting Recirc pumpspeeds andareason for this runback?
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| M Reason for Runback A. 30% Maintain adequate Recircpump NPSH B. 30% Prevent damage toReactorvessel internals C. 44% Maintain adequate RecircpumpNPSH D. 44% Prevent damage toReactorvessel internals
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| Proposed Answer: A Explanation: Under scram conditions with Reactor water level stabilizedat200"using Feedwater, total Feedwater flow isless than 20%ofrated. This initiates speed Recirc limiter
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| #1,which causes a runback to30%speed. Oneofthereasons for this runbackistoensure adequate NPSH to the Recirc pumps.
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| B.incorrect -
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| Prevent damage toReactor vessel internalsisnota reason for thisrunback.
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| Plausible because lowering Recirc flow through theReactor vesseldoes reducestress to manyReactor vessel internal components andoneother reason therunback for is preventing bearing damage toRecirc pumps.
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| C.Incorrect -
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| Recirc pumpsrunback to30%,not44%.Plausible becausethereisa 44%
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| runback that occurs under other conditions.
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| D. Incorrect -
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| Recirc pumps runback to 30%, not 44%.Plausible becausethereisa44%
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| runback that occurs under other conditions. Prevent damage toReactor vesselinternals is not areason for thisrunback. Plausible because lowering Recirc flow theReactor through vessel doesreduce stress tomanyReactor vessel internal components andoneother reason for the runback ispreventing bearing damage to Recirc pumps.
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| Technical Reference(s):OP-27, SDLP-021 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-021 1.05.b.2 Question Source: New Question History:
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| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content: 55.41(3)
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| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
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| Level RO Tier # 1 Group # 1 K/A# 295016 AK3.01 Importance Rating4.1 Control RoomAbandonment Knowledge ofthereasons for thefollowing responses asthey toCONTROL apply ROOM ABANDONMENT: Reactor SCRAM Proposed Question: #6 Theplant wasoperating at100%powerwhen the followingoccurred:
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| * ControlRoomEvacuation wasordered per AOP-43, Plant Shutdown FromOutsidethe ControlRoom.
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| a TheATCOperator hascompleted allrequired Control Roomactions.
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| a Operators have exited the MainControl Room and aretraveling tothe Remote Shutdown Panel.
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| Which oneofthe following describes theposition oftheReactorMode Switch andthereason for this position?
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| TheReactor ModeSwitch isin...
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| A. SHUTDOWN toinsert all rods control prior toleaving theControl Room.
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| B. SHUTDOWN toallow enabling controlsatthe Remote ShutdownPanel.
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| C. RUNtoavoid initiating a planttransientprior toassuming from control theRemote Shutdown Panel.
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| D. RUNbecause theplant isscrammed using only the scrampushbuttonstoprovide a
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| redundant MSIVclosure signal.
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| Proposed Answer: D Explanation: AOP-43 requires scramming theReactor priortoleaving theControl Room,but leaving the Reactor ModeSwitch inRUNtoprovide a redundant closure tothe signal MSIVs.
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| A. IncorrectThe -
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| Reactor Modeswitch remains inRUN.Plausible becausethe is Reactor scrammed, which normally results inplacing theReactor ModeSwitch inSHUTDOWN.
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| B.Incorrect -
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| The Reactor Modeswitch remains inRUN.Plausible becausetheReactor is scrammed, whichnormally results inplacing theReactor ModeSwitch inSHUTDOWN.
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| Also plausible because action is required toenable controlsattheRemote ShutdownPanel.
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| C.Incorrect -
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| TheReactoris scrammed, thereby initiating a plant prior transient, toassuming control from theRemote Shutdown Panel.Plausible because AOP-43 does haveactions to initiate ascram from outsidethe Control Room andit isgenerally desired tonotinitiate plant transients whencontrol isdegraded.
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| Technical Reference(s): AOP-43 Proposed references tobeprovided toapplicants during examination: None Learning Objective: LP-AOP1.03.a Question Source: Bank NMP12009 Cert #46 Question History:
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| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(10)
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| Comments:
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| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
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| Level RO Tier # 1 Group # 1 K/A# 295018 AK1.01 Importance Rating3.5 Partial orCompleteLoss ofCCW Knowledge oftheoperational implications ofthefollowing concepts asthey apply to PARTIAL ORCOMPLETE LOSS OFCOMPONENT COOLING WATER:Effectson component/system operations Proposed Question: #7 Theplant isoperating at100%power when all Reactor BuildingClosedLoop (RBCLC)
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| Cooling pumps become unavailable.
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| Which oneofthe followingidentifies aload that CANNOT have coolingrestored from Emergency Service Water?
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| A. DrywellVentilation Coolers B. DrywellEquipment Drain SumpCooler C. Reactor Water Cleanup PumpCoolers D. ControlRodDrive Hydraulic PumpCoolers
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| Proposed Answer: C Explanation: Uponcomplete lossofall RBCLCpumps, ESWcanbealigned tosupply cooling water tomany loads. Ofthe g ivenloads, only Water Reactor Pump Cleanup CANNOT Coolers besupplied with cooling from ESW.
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| A. Incorrect -
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| This load can besupplied from ESW.Plausible isnormally because it supplied byRBCLC andnot allRBCLC loads canbesupplied from ESW.
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| B.Incorrect -
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| This load can besupplied from ESW.Plausible because it isnormally supplied byRBCLC andnotall RBCLC loads canbesupplied from ESW.
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| D.Incorrect -
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| This load can be supplied from ESW.Plausible isnormally because it supplied byRBCLC andnotall RBCLC loads can besuppliedfrom ESW.
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| Technical Reference(s): AOP-11 Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: SDLP-12 1.10.a Question Source: Bank -2010NRC#7 Question History: 2010NRC#7 Question CognitiveLevel:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(4)
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| Comments:
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| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
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| Level RO Tier # 1 Group # 1 K/A# 295019 AA1.01 Importance Rating3.5 Partial orCompleteLoss ofinstrument Air Ability tooperate and/ormonitor the following asthey apply toPARTIAL ORCOMPLETE LOSSOFINSTRUMENT AIR: Backup air supply Proposed Question: #8 Theplant isoperating at100%power with the following:
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| a AirCompressor A isoperating.
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| a AirCompressor B isinstandby asthe15 standby compressor.
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| a AirCompressor C isinstandby asthe 2nd Sta@ WWeSE Then, the followingoccur:
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| a Elevated levels ofair leakage have been causing extended loading of AirCompressor A.
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| a Thebreaker forAir Compressor A trips duetomotor overload.
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| a Airpressure is100psig andlowering slowly.
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| Which oneofthe following describes the response ofAir Compressors B and C?
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| A. Both AirCompressors B andC start duetoanAir Compressor A breaker position signal.
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| B. AirCompressor B starts duetoanAir Compressor A breaker positionsignal. Air Compressor C starts duetoa low air pressure signal.
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| C. AirCompressor B starts duetoa lowair pressure signal. Air Compressor C remains in standby.
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| D. Both AirCompressors B andC start duetoa lowair pressure signal.
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| Proposed Answer: D Explanation: Following trip ofthe running Air Compressor, the standby will Compressors Air start ifair pressure drops far enough. Neither the1st nor2ndstandby AirCompressor will automatically start basedona breaker position signalfromthe trippedAirCompressor.
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| The1st standby Air Compressor starts whenair pressure lowers to107psig. The2ndstandby Air Compressor starts ifairpressure lowers to104psig.
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| A.Incorrect -
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| Air Compressors B andC have bothstarted,but duetoa lowairpressure signal, nota breaker position signal.
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| B.Incorrect -
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| Air Compressor B hasstarted, butduetoa lowair signal, pressure nota breaker position signal.
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| C.incorrect -
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| Air Compressor B has started duetoa low airpressure signal (107psig),
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| butso hasAir Compressor C (104 psig).
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| Technical Reference(s): OP-39, ARP 09-6-2-08 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-39 1.05.c.3 Question Source: Bank 16-1 NRC#45 Question History: 16-1 NRC#45 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(4)
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| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
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| Level RO Tier # 1 Group # 1 K/A# 295021 AA1.02 Importance Rating3.5 LossofShutdown Cooling Ability tooperate and/or monitor thefollowingasthey apply toLOSSOFSHUTDOWN COOLING: RHR/shutdown cooling Proposed Question: #9 Theplant isshutdown for a refueling outage with the following:
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| a RHRloop B isoperating inthe Shutdown Cooling (SDC) lineup.
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| a ReactorWater Recirculation (RWR) pump A isrunning andRWRpumpB issecured.
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| a Reactor water level is217inches.
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| Then, 10300 and10500 buses de-energize duetoasustained electrical fault.
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| Which oneofthe following describes the impact onreactor coolant temperature and indication theassociated reason?
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| Reactor coolant temperature indication..
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| A. will remain validduetosufficient SDCflow.
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| B. will remain validduetosufficient RWRflow.
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| C. will remain validduetosufficient natural circulation.
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| D. isNOTassured toremain validunder these conditions.
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| Proposed Answer: D Explanation: ForReactor coolant temperature indications toremain valid, flow sufficient throughthe Reactor mustbemaintained toprevent thermal stratification. Therearethree recognizedmethods toassure valid Reactorcoolant temperature indications: flow maintain with anRWRpump, maintain flow with anRHRpumpintheSDClineup, and/or maintainReactor water level greater than 234.5inches toprovide adequate natural circulation. of10300 Theloss busresults inlossof RWR pumpA.Theloss of10500 busresults inloss ofRPSA,which also causes a loss ofSDC. Since Reactor water level isbelow 234.5 inches, flow insufficient through the core exists to prevent thermalstratification andinvalid Reactor coolant temperature indications.
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| Note: Thequestion meets theK/A by giving a loss ofloss ofShutdown Cooling(duetoloss of 10500 bus) and requiring the candidate tobe able to monitor theRHR/shutdown cooling response (isolation ofSDCduetoRPS A loss) andresulting temperature indication impact.
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| A. Incorrect -
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| SDCflow islost duetolossof 10500 bus, which causes loss ofRPSA andloss ofSDC.Plausible because RHRloop B still has apumpwith power available.
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| B. Incorrect -
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| RWRflow islost duetoloss of10300 bus. Plausible because this wouldbe correct iftheinitial status ofRWRpumps wereswapped.
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| C.Incorrect -
| |
| Since Reactor water level isbelow 234.5 inches, circulation insufficient natural exists toassure accurate Reactor coolant temperature indications. Plausiblebecause Reactor water levelishigher than thenormal band.
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| Technical Reference(s): AOP-30 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-10 1.09.e Question Source: Bank16-1 NRC#40 Question History: 16-1 NRC#40 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(3)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 295023 AK2.05 Importance Rating3.5 Refueling Accidents Knowledge oftheinterrelations between REFUELING ACCIDENTS andthefollowing:
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| Secondary containment ventilation Proposed Question: #10 Theplant isoperating at100%power with the following:
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| * ISFSI cask loading activities inprogress.
| |
| a 17RM-456A, Refuel Floor Exhaust Radiation Monitor A,spikes andthen upscale fails downscale.
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| Then, anirradiated fuelbundle isdropped, resulting inthe following:
| |
| a 17RM-456B, Refuel Floor Exhaust Radiation Monitor B, indicates 2x104 cpmandstable.
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| a 17RM-452A, Below Refuel Floor Exhaust Radiation Monitor A, indicates 30cpmand stable.
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| a 17RM-452B, Below Refuel Floor Exhaust Radiation Monitor B,reads 200cpmand stable.
| |
| Which oneofthe following describes theresponse oftheReactor Building (RB)
| |
| Ventilation system?
| |
| RBVentilation train(s)...
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| A. A isolates, only.
| |
| B. B isolates, only.
| |
| C. A andB both isolate.
| |
| D. A andB both remain inservice.
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| | |
| Proposed Answer: C Explanation: 17RM-456A andB (Refuel Floor Exhaust Radiation Monitor) setpoints are:
| |
| a Downscale/inop -
| |
| 10cpm a High 1x103 cpm(EPIC only) a High 5x103 cpm a Hi-Hi -
| |
| 1x104 cpm inthe event ofhigh-highradiation oneither channel ordownscale/inop onboth a RB channels, Ventilation isolationsignal w ill be generated. Therefore, with >1x104 17RM-456B cpm,both RB Ventilation trainsisolate.
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| A. Incorrect -
| |
| Both trains isolate.Plausible that the A train would isolate onupscale/downscale failure andB train would notisolate until 17RM-456B indicated higher.
| |
| B. Incorrect -
| |
| Bothtrains isolate. Plausible that the B trainwould isolate on17RM-456B indication but A would not isolate with the downscale failure.
| |
| D. Incorrect -
| |
| Bothtrains isolate. Plausible that isolation logic wouldn't bemadeupfor either train with downscale failure and17RM-456Bat current indication.
| |
| Technical Reference(s):OP-51A, ARP09-3-2-40, SDLP-66A Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-66A 1.14 Question Source: Bank 9/12 NRC#10 Question History: 9/12NRC#10 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 295024 EK1.01 importance Rating4.1 High Drywell Pressure Knowledge oftheoperational implications ofthefollowing concepts astheyapplyto HIGHDRYWELL PRESSURE: Drywell integrity:Plant-Specific Proposed Question: #11 Theplant hasexperienced a loss ofcoolant accident with the following:
| |
| * Reactorwater levelis5"andrising slowly with Condensate pumpB injecting.
| |
| a Core Spray pumpA andHPCIhave justbeen made available for injection.
| |
| * HPCIsuction isaligned tothe CSTsandCANNOT beswappedtothe Torus.
| |
| * NOother injection sources areavailable.
| |
| * Drywellpressure ischallenging thePrimary Containment Pressure Limit (PCPL).
| |
| Which oneofthe following identifies the preferred injection source(s) under these in conditions, accordance with EOP-2, R PV Control?
| |
| A. HPCI B. Core Spray pumpA C. Condensate pumpB D. HPCIandCondensate pumpB
| |
| | |
| Proposed Answer: B Explanation: EOP-2contains the following guidance:
| |
| IF THEN Primary containment waterlevel and pressuresanno.t bemaintained below Terminate injectioninto theRPV thePrimary Containment Pressure ,, ,g 3 1.1mit - ,
| |
| Adequate corecooling can beassured Condensate pumpB injects from the Hotwell, which isexternal tothe primary containment.
| |
| With HPCIaligned tothe CSTsandunable toberealignedtothe Torus, italso injects froma source external tothe primary containment. Core Spray pumpA injects from the T orus,which isnotexternal tothe primary containment.Therefore, the preferred injectionsource, withPCPL being challenged, isCore Spray pumpA.
| |
| A. Incorrect -
| |
| Core Spray isthe preferred injectionsource. Plausible because HPCIwould be apreferred injection source ific tould berealignedto take suction from the Torus. Also plausible because HPCIcaninject athigher Reactorpressures, hasfiner control, andis from arelatively cleaner source. Alsoplausible because Core Spray is specifically not preferred insomesituations (ATWS).
| |
| C. Incorrect -
| |
| Core Spray isthepreferred injectionsource. Plausible because Condensateis already injecting, hasfiner control, andis from arelatively cleaner source. Also plausible because Core Spray isspecifically not preferred insomesituations(ATWS).
| |
| D. Incorrect -
| |
| Core Spray isthe preferred injectionsource. Plausible because HPCIwould be a preferred injection source ific tould berealigned totake suction from the Torus. Also plausible because HPCIandCondensate have finer control andare from relatively cleaner sources. Also plausible because Core Spray isspecifically not preferred insome situations (ATWS).
| |
| Technical Reference(s):EOP-2 Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11b 1.07 Question Source: Bank SSESLOC28R NRC#39(2017)
| |
| Question History: SSESLOC28R NRC#39(2017)
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content: 55.41(10)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 295025 EA1.04 Importance Rating3.8 High Reactor Pressure Ability tooperate and/ormonitor thefollowingasthey applytoHIGHREACTOR PRESSURE: HPCI: Plant-Specific Proposed Question: #12 A scram hasoccurred with the following:
| |
| * MSlVs are closed.
| |
| a HPCIautomatically started andisthe only available injectionsource.
| |
| * HPCIinjection hasbeen throttledto1000 gpm to theReactorwith the controller in AUTO.
| |
| a Reactorwater level is180inches andslowly rising.
| |
| * Reactor pressure is900psig andslowly rising.
| |
| Which oneofthe following describes theresponse ofHPCIflow rate if Reactor pressurerises to 1100 psig?
| |
| HPCIflow ratewill...
| |
| A. lowerbecause HPCIturbine speed iscontrolled ata constant value.
| |
| B. lowerbecause the design discharge pressure range oftheHPCIpumpisexceeded.
| |
| C. remain approximately constant because thecontrol system will throttlethegovernor based onaflow feedback signal.
| |
| D. remain approximately constant because rising Reactor steamsupply pressure balances pumpdischarge rising pressure without theneedfor governor adjustment.
| |
| | |
| Proposed Answer: C Explanation: TheHPCIpumpisdesigned tosupply 4250gpmover a Reactor range pressure from 150 to 1195 psig. With rising Reactor pressure, HPCIflow willtendtolower.
| |
| However, with the controller inAUTO,the HPCIgovernor valve willbeautomatically tomaintain adjusted constant flow based onaflow feedback signal.
| |
| A. Incorrect -
| |
| Flow will remain approximately constant. WheninAUTO,the controller maintains constant flow, not speed.
| |
| B.Incorrect -
| |
| Flow willremain approximately constant. HPCIisrated for4250gpmupto1195 psig.
| |
| D.Incorrect -
| |
| With rising Reactor pressure, HPCIflow willtend tolower based onthenatural interplay ofsteam supply pressure vs. pumpdischarge pressure. Governorresponse is required tomaintain flow approximately constant over this 200psig inReactor change pressure.
| |
| Technical Reference(s): OP-15 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-23 1.05.a.22 Question Source: Bank 14-2 NRC#46 Question History: 14-2 NRC#46 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(8)
| |
| Comments:
| |
| | |
| I ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 295026 EK3.01 importance Rating3.8 Suppression Pool High Water Temperature Knowledge ofthereasons for thefollowing responses astheyapply toSUPPRESSION POOLHiGHWATER TEMPERATURE: Emergency/normal depressurization Proposed Question:#13 Which oneofthe following describes (1)whenEmergency RPVDepressurization is required based onhigh Torus temperature and (2)thebasis forthis requirement, inaccordance with EOP-4, Primary Containment Control?
| |
| A. (1)Before Torus temperature reaches theBoron Injection Initiation Temperature (BIIT)
| |
| (2)Maintain adequate NetPositive Suction Head(NPSH) for ECCS pumps B. (1)Before Torus temperature reaches theBoron Initiation Injection Temperature (BilT)
| |
| (2)Avoid failureoftheContainment orequipment inside theContainment C. (1)WhenTorus temperature andRPVpressure bemaintained cannot below the Heat Capacity Temperature Limit (HCTL)
| |
| (2)Maintain adequate NetPositive Suction Head(NPSH) for ECCSpumps D. (1)WhenTorus temperature andRPVpressure bemaintained cannot below theHeat Capacity Temperature Limit (HCTL)
| |
| (2)Avoid failureoftheContainment orequipment inside theContainment
| |
| | |
| Proposed Answer: D Explanation: TheEOP-4 Torus temperature leg requires Emergency RPVDepressurization if Torus temperature andRPVpressure cannot bemaintained below theHeat Capacity Temperature Limit (HCTL). Thebasis istonotraise Torus water orpressure temperature above limitsbefore the rate ofenergy transfer from theRPVtothecontainment isgreater than the capacity ofthe containment vent, such thatfailure ofthecontainment andequipment inside thecontainment isavoided.
| |
| A. Incorrect -
| |
| EnteringEOP-2, not Emergency RPVDepressurization, isrequired before Torus temperature reaches BilT. ECCS pumpNPSHislowered asTorus rises, temperature however itisnot thespecific basis for theEmergency RPVDepressurization requirement.
| |
| B. incorrect -
| |
| Entering EOP-2,not Emergency RPVDepressurization, before isrequired Torus temperature reaches BIIT.
| |
| C.Incorrect -
| |
| ECCSpumpNPSHislowered asTorus temperature rises, however it isnot the specific basis fortheEmergency RPV Depressurization requirement.
| |
| Technical Reference(s): EOP-4,MIT-301.11e Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11e 4.05 Question Source: Bank 17-1 NRC#45 Question History: 17-1 NRC#45 Question Cognitive Level:MemoryorFundamental Knowledge 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 295028 2.2.42 Importance Rating3.9 HighDrywell Temperature Ability torecognize system parameters that areentry-level conditions forTechnical Specifications Proposed Question: #14 Theplant isoperating at50%power with the following:
| |
| = A dualseal failureoccurred onRecircpump A.
| |
| e RecircpumpA hasbeentripped andisolated.
| |
| = Drywellpressure is1.85 psig andstable.
| |
| = Drywellaverage airtemperature is1450F andstable.
| |
| Which oneofthe following describes the status oftheLimiting Condition for Operation for (LCO)
| |
| Technical Specifications 3.6.1.4, Drywell Pressure, and3.6.1.5,Drywell AirTemperature?
| |
| M M A. NOTexceeded NOTexceeded B. NOTexceeded Exceeded C. Exceeded NOTexceeded D. Exceeded Exceeded
| |
| | |
| Proposed Answer: B Explanation: Drywellpressure isbelow the LCO3.6.1.4 of1.95 limit psig. average Drywell air temperature isabove the LCO3.6.1.5 limit of1350F.
| |
| A. incorrect Drywell average air temperature isabove theLCO3.6.1.5 of1350F.
| |
| limit Plausible because Drywell average air temperature isonlyslightly the above limit.
| |
| C.incorrect -
| |
| Drywell pressure isbelow theLCO3.6.1.4 of1.95 limit Plausible psig. because Drywell pressure is elevated and close tothe limit. Drywell air average is temperature above theLCO3.6.1.5 limit of1350F. Plausible because Drywell average air is temperature only slightly above thelimit.
| |
| D. Incorrect -
| |
| Drywell pressure is below the LCO3.6.1.4 limit psig.
| |
| of1.95 because Plausible Drywell pressure iselevatedand close tothe limit.
| |
| Technical Reference(s):Technical Specifications 3.6.1.4 and3.6.1.5 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-16A 1.16 Question Source: Modified BankSSESLOC27 NRC#65(2017)
| |
| Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content: 55.41(10)
| |
| Comments:
| |
| | |
| SUSQUEHANNA STEAM ELECTRIC STATION LOC27 NRCINIT1AL LICENSE EXAMINATION REACTOR OPERATOR WRITTEN EXAMINATION Examination OutlineCross-reference: Level RO SRO 295010High Drywell Pressure /5 Tier # 1 2.2.22 Equipment Control: Knowledge oflimiting conditions Group # 2 foroperationsand safety limits.
| |
| K/A # 295010 Importance Rating4.0 Unit1is in Mode 3with the following:
| |
| Adual seal failure occurred onReactor Recirculation pump (RRP) 1A.
| |
| RRP1Ahas been tripped andisolated.
| |
| Drywell pressure is2.2 psig, steady.
| |
| * Drywell average temperature is145F, steady.
| |
| Which oneofthe followingdescribes thestatus ofthe Limiting Condition for Operation (LCO) for Technical Specifications3.6.1.4, Containment Pressure, and3.6.1.5, Drywell Air Temperature?
| |
| LCO3.6.1.4, Containment.Pressure LCO3.6.1.5, Drywell Air Temperature A. NOTexceeded NOTexceeded B. NOTexceeded Exceeded C. Exceeded NOTexceeded D. Exceeded Exceeded
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 1 Group # 1 K/A# 295030 EK1.02 Importance Rating3.5 LowSuppression Pool Water Level Knowledge oftheoperational implications ofthefollowing concepts astheyapplyto LOWSUPPRESSION POOLWATER LEVEL:PumpNPSH Proposed Question: #15 Theplant hasexperienced a seismic event and loss ofcoolant accident with following:
| |
| the a Reactor water level is-10" andslowlylowering.
| |
| a Reactor pressure is100psig andslowlylowering.
| |
| a Torus pressure is6 psig andslowly rising.
| |
| a Torus water level is11' andstable.
| |
| a RHRpumps A andC have just been madeavailable for injection.
| |
| a NOother injection sources are available.
| |
| Note: TheRHRPumpNPSHLimit isprovided onthe following page.
| |
| Which oneofthe following describes:
| |
| (1) theappropriate Torus Overpressure Linetouseonthe RHRPumpNPSH Limit and (2) whether orNOTRHRflow isallowed totemporarily exceed this limit, inaccordance with OP-13A, RHR LowPressure Coolant Injection?
| |
| (2)Istemporarily exceedingRHR M
| |
| A. 5 psig No B. 5 psig Yes C. 10psig No D. 10psig Yes
| |
| | |
| RHRPUMPNPSHLIMIT
| |
| ---1 250.00
| |
| -1 Pump Opera9ng 240.00 2Pumps Operategl 230.00
| |
| ~
| |
| u.
| |
| 220.00 gF 210.00 ' -- ----- -
| |
| 1 '
| |
| overpressure*
| |
| tu
| |
| @200.00 190.00 "
| |
| 5 Overpressure*
| |
| D g 1s0.00. 4 o:
| |
| 170.00 E 160.00 150,00 0 Overpressure*
| |
| 140.00 130.00 0 1 2 3 4 5 6 7 8 9 10 11 SINGLE LOOPRHR FLOWPERPUMP(gpm X 1000)
| |
| Overpressure
| |
| *Torus = Torus + 0.4(Torus Pressure WaterLevel 1.92)(seewate 1)
| |
| | |
| Proposed Answer: B Explanation: Thegiven conditions result ina Torus Overpressure calculation +
| |
| of6 psig 0.4*(11'-1.92) = 9.632. Note 1ontheassociated Posted Attachment "If states thecalculated value ofTorus Overpressure falls between sets ofcurves, then usethe lower (e.g.
| |
| set.
| |
| Overpressure =2 psig, use the 0 psigcurves)", Therefore, the 5 psig curvemustbeused.This limit isnotanabsolute limit,butrather acautionregarding thepotential tocause pumpdamage.
| |
| Therefore, thelimitcan beexceeded if necessary.
| |
| A. Incorrect -
| |
| RHRflow is allowed toexceed thelimit if necessary. Plausible because if many, not most, limitsarenotallowed tobeexceeded.
| |
| C.Incorrect -
| |
| The5 psig curve must beused. Plausible because overpressure thecalculated is9.632, which isverycloseto 10. RHRflow isallowed toexceed thelimit necessary.
| |
| if Plausible because many, ifnotmost, limitsarenot allowed tobeexceeded.
| |
| D. Incorrect -
| |
| The5 psig curve mustbe used. Plausiblebecause thecalculated overpressure is9.632, which isveryclose to10.
| |
| Technical Reference(s): OP-13A Proposed references tobeprovided toapplicantsduring examination: None Learning Objective: SDLP-10 1.13.a Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 295031 2.4.34 Importance Rating4.2 Reactor LowWaterLevel Knowledge ofROtasks performed outside themaincontrol roomduring anemergency andtheresultant operational effects.
| |
| Proposed Question: #16 Theplant isoperating at25%power with the following:
| |
| A fireinthe Control Roomrequires execution ofAOP-43, Plant Shutdown FromOutside the Control Room.
| |
| a Operators have completed all required Control Room and fieldactions ofAOP-43.
| |
| a Then, asmall loss ofcoolant accident develops.
| |
| a Reactor water level is150" andlowering.
| |
| Which oneofthe following describes the ability ofHPCIandRCIC to automatically inject tothe Reactor ifReactor waterlevel continues tolower?
| |
| A. Both HPCIandRCICwill automatically inject.
| |
| B. HPCIwill automatically inject, butRCICwill NOT.
| |
| C. HPCIwill NOTautomatically inject,but RCICwill.
| |
| D. NEITHER HPCINORRCICwill automatically inject.
| |
| | |
| Proposed Answer: D Explanation: AOP-43 actions result inclosing oftheRCICtrip throttle which valve, prevents RCICfrom automatically injecting totheReactor given lowwater level.AOP-43 also actions result in taking the 23MOV-16 and-60isolation switches toLOCAL, which automatic prevents initiation ofHPCI.
| |
| A. Incorrect -
| |
| HPCI will NOT automatically inject. Plausible because this wouldbecorrect if specific action was not taken in AOP-43 toprevent HPCIinjection. RCICwill not automatically inject because operator action hasbeen taken per AOP-43toclose thetrip throttle valve. Plausible because this would becorrect ifspecific action wasnottaken in AOP-43 toprevent RCICinjection.
| |
| B. incorrect -
| |
| HPCIwill NOTautomatically inject. Plausible because this wouldbecorrect if specific action wasnot taken inAOP-43 toprevent HPCIinjection.
| |
| C.Incorrect -
| |
| RCICwill not automatically inject because operator hasbeen action takenper AOP-43 toclose the tripthrottle valve. Plausible because this would becorrectspecific if action wasnot taken inAOP-43 toprevent RCIC injection.
| |
| Technical Reference(s):AOP-43 Proposed references tobeprovided toapplicants during examination: None Learning Objective: LP-AOP 1.08 Question Source: Bank 17-2 NRC#21 Question History: 17-2 NRC#21 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 295037 EK2.03 Importance Rating4.1 Scram Condition Present andReactorPower Above APRMDownscale orUnknown Knowledge oftheinterrelations between SCRAM CONDITION PRESENT ANDREACTOR POWER ABOVEAPRMDOWNSCALE ORUNKNOWN andthefollowing: ARI/RPT/ATWS:
| |
| Plant-Specific Proposed Question: #17 Theplant isoperating at100%power withthe following:
| |
| a A malfunction occurs withtheMain Turbine pressure regulator.
| |
| * Reactor pressure risestoa high value of1170 psig andthen lowers to920psigon Turbine Bypass Valves.
| |
| Which oneofthe following describes the status ofthe Alternate Rod Insertion solenoids (ARI) andtheReactor Water Recirculation (RWR) pumps a fterthistransient?
| |
| ARISolenoids RWR Pumps A. Energized Tripped B. Energized Running C. De-energized Tripped D. De-energized Running
| |
| | |
| Proposed Answer: A Explanation: Reactorpressure risingabove 1153 psig actuates both theARIandATWS-RPT logic. The ARI logicenergizes theARIsolenoids tovent the scram air andcause header an alternate Reactor scram method. TheATWS-RPT logic tripsthe RWRpumps. There isnotime delay onthehigh pressure actuation ofARIandATWS-RPT logic.
| |
| B. Incorrect -
| |
| RWR pumps trip. Plausible because there wasnolowlevel condition, the pressure rise wasmitigated by TBVs, andthe pressure transient wasshort.
| |
| C. Incorrect -
| |
| ARIsolenoids areenergized. Plausible because there wasnolowlevel condition, the pressurerise was mitigated byTBVs, andthe pressure wasshort.
| |
| transient Also plausible because normal scram solenoids arede-energize tofunction.
| |
| D. Incorrect -
| |
| ARIsolenoids are energized. Plausible because there wasnolowlevel condition, the pressure rise was mitigated by TBVs, andthepressure wasshort.
| |
| transient Also plausible because normal scram solenoids arede-energize RWRpumps tofunction.
| |
| trip. Plausible because there wasno low levelcondition,thepressure wasmitigated rise by TBVs, andthe pressure transient wasshort.
| |
| Technical Reference(s):OP-25, OP-27 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-03C 1.05.c.8, SDLP-02H 1.05.c.2 Question Source: Bank14-1 NRC#50 Question History: 14-1NRC#50 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| I ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 295038 EK1.02 Importance Rating4.2 High Offsite Radioactivity Release Rate Knowledge oftheoperational implications ofthefollowing concepts asthey apply to HIGHOFFSITE RELEASERATE: Protection ofthegeneral public Proposed Question: #18 Theplant wasoperating at100%powerwhen the followingoccurred:
| |
| = A MainSteam leak occurred inthe Turbine Building.
| |
| * TheReactor wasscrammed.
| |
| * TheMSlVs arestuck inmid-position.
| |
| * Therunning Turbine Building Exhaust Fanhas tripped.
| |
| a Thestandby Turbine Building Exhaust Fanhasfailed toauto-start.
| |
| EOP-6, Radioactivity Release Control, hasbeen entered.
| |
| Which oneofthe following describes therequired control ofTurbine Building Ventilation, in accordance with EOP-6, andtheassociated reason?
| |
| A. RestoreaTurbine Building Exhaust Fantoservice tolimitunmonitored ground level radioactivityrelease.
| |
| B. RestoreaTurbine Building Exhaust Fantoservice toprevent equipment damage inthe TurbineBuilding.
| |
| C. Ensure Turbine BuildingVentilation issecured andisolated tocontain the steam leakto theTurbine Building.
| |
| D. EnsureTurbine BuildingVentilation issecured andisolated tolimit radioactivity total releasetothe Site Boundary.
| |
| | |
| Proposed Answer: A Explanation: EOP-6hasa step that states, "lFTurbine Building Ventilation orRadwaste BuildingVentilation is shutdown, orisolated duetohigh radiation, THENRestart theventilation system asrequired. Defeatisolation interlocks ifnecessary (EP-2)." The of restart Turbine Building Ventilation isrequired todirect anyradioactive discharge toanelevated,monitored release point instead of aground-level, unmonitored releasepoint.
| |
| B. Incorrect -
| |
| Thereason forrestarting Turbine Building Ventilation istocontrol radioactive release, not preventequipment damage inside the Turbine Building.Plausiblebecause restoring ventilation will limit temperature rise inthe Turbine Building andexhaust moisture, both ofwhich will tend toprevent equipment damage.
| |
| C.Incorrect -
| |
| EOP-6 requires Turbine Building Ventilation toberestarted, notisolated.
| |
| Plausible because forasimilarsituation intheReactor Building, ReactorBuilding ventilation isrequired tobeisolated.
| |
| D.Incorrect -
| |
| EOP-6 requires TurbineBuilding Ventilation toberestarted, notisolated.
| |
| Plausible because fora similar situation in the Reactor Building, ReactorBuilding ventilation isrequired tobeisolated.
| |
| Technical Reference(s):EOP-6, MIT-301.11G Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11G 6.04 Question Source: Bank 12-2 NRC#71 Question History: 12-2 NRC#71 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 600000AA2.14 Importance Rating3.0 Plant Fire OnSite Ability todetermine and/or interpret thefollowing asthey apply toPLANTFIREONSITE:
| |
| Equipment thatwillbeaffected byfire suppression activities ineachzone Proposed Question: #19 Theplant isoperating at100%power with the following:
| |
| * A firehasdeveloped inthe northwestportion ofReactorBuilding elevation 272'
| |
| * TheFire Brigade isfighting the fire with water from two fire hoses.
| |
| Which oneofthe following identifies equipment inthis area that maybeaffected?
| |
| A. HPCI B. RCIC C. CRDpumps D. RWCUpumps
| |
| | |
| Proposed Answer: C Explanation: CRDpumpsarelocated inthis area oftheReactor (northwest Building of portion elevation 272') andmaybeaffected bythe fire andfire suppressionactivities.
| |
| A. Incorrect HPCI isnotlocated inthis area oftheReactor because Plausible Building. this would becorrect forafire intheeast portion ofReactor 227'.
| |
| Building B.Incorrect -
| |
| RCIC is notlocated inthis area ofthe Reactor because Plausible Building. this would becorrectfor a fireinthe west portion ofReactor 227'.
| |
| Building D.Incorrect -
| |
| RWCUpumps arenotlocated inthis areaoftheReactor Plausible Building.
| |
| because this would becorrect forafire inthe south portion Building ofReactor 300'.
| |
| Technical Reference(s): SDLP-03C, SDLP-12, SDLP-13,SDLP-23 Proposed references tobeprovided to applicants duringexamination: None Learning Objective: SDLP-03C 1.11.c.3 Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(6)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 1 K/A# 700000 AK2.02 Importance Rating3.1 Generator Voltage and Electric Grid Disturbances Knowledge oftheinterrelations between GENERATOR VOLTAGE ANDELECTRIC GRID DISTURBANCES andthefollowing: Breakers, relays Proposed Question: #20 Theplant isoperatingat100%power with the following sequence:
| |
| Time (seconds) Condition(s) 0 . A fault occurs onLine 3.
| |
| . Breaker 10022, LHH-115KV LINE 3, opens.
| |
| 5 . Thefault onLine 3clears.
| |
| Line 3isenergized with normal voltage.
| |
| Which oneofthe following identifies the status ofBreaker 10022 andDisconnect 10017, NORTH-SOUTH 115KVBUSDISCSW,atTime= 120seconds?
| |
| Breaker 10022 Disconnect10017 A. Open Open B. Open Closed C. Closed Open D. Closed Closed
| |
| | |
| Proposed Answer: D Explanation: With theplant ina normal initially electricallineup, Breaker 10022 isclosed, Disconnect 10017 is closed, andthe Breaker 10022 automatic reclosure featureisenabled.
| |
| Since thefault clears inunder 10seconds andLine 3 hasnormal voltage,Breaker 10022will automatically reclose atapproximately Time = 10seconds. Since Breaker10022 isableto close atthis time, Disconnect 10017 will remain closed throughout thetransient.
| |
| A. Incorrect -
| |
| Breaker 10022 will beclosed. Plausible because thiswould becorrect ifthe automatic reclosurefeature wasnormally disabled, orifthe fault did for notclear a longer period oftime such that automatic reclosuresattempted andthen lockedout.Disconnect 10017 will beclosed. Plausible because this would becorrect ifthenormal lineup electrical hadthis disconnect open, orin other fault responses.
| |
| B. Incorrect -
| |
| Breaker 10022 willbe closed. Plausiblebecause thiswouldbecorrectifthe automatic reclosure feature wasnormally disabled, orif the fault didnotclear fora longer period oftime such that automatic reclosures attempted andthen lockedout.
| |
| C.Incorrect -
| |
| Disconnect 10017 beclosed. Plausible because will this wouldbecorrectif the normal electrical lineup hadthis disconnect open, orin other fault responses.
| |
| Technical Reference(s):SDLP-71D Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-71D Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| I ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 2 K/A# 295013 AK2.01 Importance Rating3.6 High Suppression Pool Water Temperature Knowledge oftheinterrelations between HIGHSUPPRESSION POOLWATER TEMPERATURE andthefollowing: Suppression pool cooling Proposed Question: #21 Theplant isoperating at90%power with the following:
| |
| * HPCIsurveillance testing hasjust been completed inaccordance with ST-4N, HPCI Quick-Start, In-service, andTransient Monitoring Test.
| |
| a RHRLoop A is operating inTorus Cooling.
| |
| = RHRpumpA is operating.
| |
| a RHRpumpC issecured.
| |
| * RHRSW flow hasbeenestablished.
| |
| a Lake water temperature is370F.
| |
| a Torus temperature is800F andslowly lowering.
| |
| Which oneofthe following identifies thelowest allowable Torustemperature and whether RHR pumpC isallowed tobestarted toraise the cooldown rate,inaccordance with OP-13B, RHR-Containment Control?
| |
| Thelowest allowable Torus temperature is...
| |
| A. 500F. RHRpumpC isallowed tobestarted.
| |
| B. 500F. RHRpumpC isNOTallowed tobestarted.
| |
| C. 720F. RHRpumpC isallowed tobestarted.
| |
| D. 720F. RHRpumpC isNOTallowed tobestarted.
| |
| | |
| Proposed Answer: C Explanation: OP-13B states that thelowest allowable Torus 720F.
| |
| temperature RHRpumpC isallowed to bestarted toraise thecooldown rate.
| |
| A. Incorrect The -
| |
| lowest allowable Torus temperature 720F. Plausible 500F because isa temperaturelimit used inother plant procedures (Condenser waterbox temperature control, Offgas). RHRpump C isallowedtobestarted toraise the cooldown Plausible rate. that only oneRHRpump would beallowed toberun innon-emergency conditions.
| |
| B.Incorrect -
| |
| Thelowest allowable Torus temperature 720F. Plausible 500F because isa temperature limitusedin other plant procedures (Condenser waterbox temperature control, Offgas).
| |
| D. Incorrect -
| |
| RHRpumpC is allowed to bestarted toraise the cooldown Plausible rate. that only oneRHRpumpwould beallowed toberuninnon-emergency conditions.
| |
| Technical Reference(s): OP-13B Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-10 1.13 Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(8)
| |
| Comments:
| |
| | |
| I ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 2 K/A# 295020 AK1.02 Importance Rating3.5 Inadvertent Containment Isolation Knowledge oftheoperational implications ofthefollowing concepts astheyapply to INADVERTENT CONTAINMENT ISOLATION: Power /reactivitycontrol Proposed Question: #22 Theplant isoperating at20%power with the following:
| |
| * TheReactor ModeSwitch isinRUN.
| |
| a An inadvertent isolation signal causes the following valvestoclose:
| |
| o MSlV 29AOV-80A o MSlV29AOV-80C o MSIV 29AOV-86B Which oneofthe following describes Reactor power asindicated on theAPRMs one(1) minute after this transient begins?
| |
| APRMswill indicate...
| |
| A. approximately 0%.
| |
| B. greaterthan 0%but less than 20%.
| |
| C. approximately 20%.
| |
| D. greaterthan 20%.
| |
| | |
| Proposed Answer: A Explanation: Onanisolation signal, MSIVs arerequired toclose within5seconds. TheMSIV closure scram logic is arranged sothat withtheModeSwitch inRUN,ascram will occurifan MSIVisclosed inatleast 3ofthe 4 Main Steam Lines. Thegiven are valves distributed between MainSteam LinesA,B,andC,therefore a Reactor scram occur, will eventhough 20%
| |
| Reactor steam flow iswell within the capacity ofa single Main Steam Line.APRMsdrop to0%
| |
| following theReactor scram.
| |
| B. Incorrect -
| |
| Reactor power lowers to 0%onAPRMsduetoascram. Plausible becauseCore Thermal Power willremain above 0%for anextended period oftime duetodecay heat.
| |
| C. Incorrect -
| |
| Reactor powerlowers to0%onAPRMsduetoascram. Plausible becauseif only twoMain Steam Lines isolated, theReactor would NOTscram andpower would stabilize back atapproximately20% within oneminute. While asingle MainSteam Line can handle 20%Reactor steam flow, the RPS logic still will enforce ascram inthis situation.
| |
| D. Incorrect -
| |
| Reactor power lowers to0% on APRMs duetoa scram. Plausible because Reactor power willinitially rise asMSIVs stroke closedandReactor pressure however rises, the scram occurs well within oneminute.While asingleMain Steam Line canhandle20%
| |
| Reactor steam thef low, RPSlogic will still enforce a scram inthis situation.
| |
| Technical Reference(s): OP-1 Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: SDLP-29 1.05.b.1 Question Source: Bank 14-2 NRC#63 Question History: 14-2 NRC#63 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(5)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 2 K/A# 295029 EA1.03 Importance Rating2.9 High Suppression Pool Water Level Ability tooperate and/or monitor thefollowingasthey apply toHIGHSUPPRESSION POOLWATERLEVEL: RHR/LPCI Proposed Question: #23 Theplant isoperating at75%power withthe following:
| |
| * AnSRVinadvertently opened andwasclosed byOperators.
| |
| * Torus water level isnow14.1 feet andstable.
| |
| Which oneofthe following describes themethod required to lower Torus in level, water accordance with EOP-4, Primary Containment Control?
| |
| A. RunanRHRpumptotransfer Torus water toRadwaste B. Runa Core Spray pumptotransfer Torus water toRadwaste C. Gravitydrain through RHRpiping toReactor Buildingdrains D. Gravitydrain through Core Spray piping toReactor Building drains
| |
| | |
| Proposed Answer: A Explanation: EOP-4directs useofOP-13B tolower Torus water level.
| |
| OP-13B G.1 sections andG.2utilize a running RHRpumptotransfer water Radwaste.
| |
| B. Incorrect RHR, notCore Spray isused. Plausible because Core Spray takes also a suction onthe Torus.
| |
| C.Incorrect -
| |
| Torus water is actively pumped, notgravity drained. because Plausible the correct method does utilize the Reactor Buildingdrain header flow ofthe aspart path,andit would bephysicallypossible togravity drain toReactor Building drains andthenpumpthose drains using normal sump pumps.
| |
| D.incorrect -
| |
| Torus water isactively pumped using RHR,not gravity Plausible drained.
| |
| because thecorrect methoddoes utilize the Reactor Building drainheader ofthe aspart flow path, andit would bephysically possible togravity drain Building toReactor drainsand then pumpthose drains using normal sump pumps.Also plausible Core because Spray also takes a suction onthe Torus.
| |
| Technical Reference(s): EOP-4,OP-13B Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11e 4.05 Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(9)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 1 Group # 2 K/A# 295032EK3.01 Importance Rating3.5 High Secondary Containment AreaTemperature Knowledge ofthereasons for thefollowing responses asthey apply toHIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Emergency/normal depressurization Proposed Question: #24 Which oneofthe following describes a reason for Emergency RPVDepressurization duetohigh Secondary Containment temperature, inaccordance with EOP-5, Containment Secondary Control?
| |
| Emergency RPVDepressurization isbased onconcernsfor.=.
| |
| A. habitabilityoftheControl Room B. operabilityofthePrimary Containment C. lossofequipment locatedintheReactor Building D. lossofnormal personnel access totheReactor Building
| |
| | |
| Proposed Answer: C Explanation: Oneofthereasons for Emergency RPVDepressurization duetohigh Secondary Containment temperatures isloss ofequipment located intheSecondary Containment.
| |
| A. Incorrect This isnot astated reason for Emergency RPVDepressurization duetohigh Secondary Containment temperatures. Plausible because anun-isolable primary system discharging into the Reactor Building does leadtemperature to and concerns radiation that could impact theControl Room.
| |
| B. Incorrect -
| |
| This isnot a stated reason for Emergency RPVDepressurization duetohigh Secondary Containment temperatures. Plausible because high inthe temperatures Secondary Containment do impact the Primary Containment since structure, it islocated within the Secondary Containment.
| |
| D. Incorrect -
| |
| This isnot astatedreason for Emergency RPVDepressurization duetohigh Secondary Containment temperatures. Plausible because high inthe temperatures Secondary Containment doimpact the ability of personneltoenter thebuilding.
| |
| Technical Reference(s):MIT-301.11f Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11f 1.07 Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 2 K/A# 295009 AA2.01 Importance Rating4.2 LowReactor Water Level Ability todetermine and/or interpret thefollowing asthey apply toLOWREACTOR WATERLEVEL: Reactor water level Proposed Question: #25 Theplant hasexperienced a loss ofcoolant accident with thefollowing:
| |
| a Reactorwater level is-10" andslowlylowering.
| |
| a Reactor pressure is150psig andslowlylowering.
| |
| a CRDpumpA isinjecting tothe Reactor.
| |
| a NOother Reactor injection sources are available.
| |
| Which oneofthe following describes thestatus ofAdequate Core Cooling (ACC)?
| |
| ACCis.
| |
| A. NOTpresently assured.
| |
| B. presently assured. ACCwill befirstlost ifReactor water levellowers below -19".
| |
| C. presently assured. ACCwill befirstlost ifReactor water levellowers below -31.5" D. presently assured. ACCwill befirstlost ifReactor water levellowers below -44.5".
| |
| | |
| Proposed Answer: B Explanation: With Reactor water levelbelow topofactive fuel(0"), but above ACCis
| |
| -19",
| |
| presently assured via "Steam Cooling with injection". WithnoCore Spraypumpsrunning and CRDinjection, ACC will firstbelost if Reactor water levelreaches -19".
| |
| A. Incorrect -With Reactor water levelbelow top ofactive fuel (0"), but above ACCis
| |
| -19",
| |
| presently assured via "Steam Cooling with injection". Plausible because thepreferred source ofACC,"Submergence", isnotcurrently inplace (<0").
| |
| C. Incorrect -
| |
| With noCore Spray pumpsrunning andCRDinjection, ACCwill first belost if Reactor water level reaches -19". Plausiblebecause this would becorrectthere if wasno injection tothe Reactor.
| |
| D. Incorrect -
| |
| With noCore Spray pumps running andCRDinjection, ACCwillfirst belost if Reactor water level reaches -19". Plausible because this would becorrect if one atleast Core Spray pumpwasrunning ator above 4725 gpm.
| |
| Technical Reference(s): EOP-2, EP-1 Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT301.11C 2.04 Question Source: Modified Bank9/12 NRC#22 Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES401 Written Examination QuestionWorksheet FormES-4015 Examination Outline Cross
| |
| | |
| ==Reference:==
| |
| Level RO Ter# t Group # 2 K/A# 295009AA2.01 importance Rating4.2 Low Reactor Water Level Abilityto determine and/orinterpret thefollowing astheyapply toLOWREACTOR WATER LEVEL:Reactor waterlevel Proposed Question: #22 ThePlant hasexperienced a loss ofcoolant accident.
| |
| Core Spray Pump(CSP) A'isthe galg injecting sourceofwater.
| |
| * RPVlevel: -10 inches andlowering
| |
| * CSP'A' flow rate: 5075 gpm
| |
| * Safety Relief Valves: Sevenopen Based ontheabove conditions.which oneofthefollowing describes thestatus of~Adequate Core Cooling" (ACC)?
| |
| ACC...
| |
| A. isNOTpresently assured.
| |
| B. ispresently assured.ACCwill befirst if lost RPVlevel reaches -19inches.
| |
| C. ispresently assured.ACCwill befirst if lost RPVlevel reaches -31.5 inches.
| |
| D. ispresenny assured. ACCwill befirst if lost RPVlevel reaches -445inches.
| |
| JAF12-2NRC
| |
| | |
| ES-401 Written Examination Question Worksheet FormES4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 1 Group # 2 K/A# 295035 2.4.1 Importance Rating4.6 Secondary Containment High Differential Pressure Knowledge ofEOPentryconditions andimmediate action steps.
| |
| Proposed Question: #26 Theplant isoperating at100%powerwith thefollowing:
| |
| a A steam leakhasdeveloped from the RCIC supplypiping intotheReactorBuilding.
| |
| a Reactor Building ventilation exhaust radiation is3x 103 cpmandslowly rising.
| |
| a RCICDrywell entrance area temperatureis 1400F andslowly rising.
| |
| a Reactor Building differential pressure is0"H20 and stable.
| |
| Note: A portion ofEOP-5, Secondary Containment Control, isprovided onthe following page Which oneofthe followingidentifies the number ofentry conditions met for EOP-5, Secondary Containment Control, andEOP-6, Radioactivity Release Control?
| |
| EOP-5 EOP-6 A. 3 1 B. 3 0 C. 2 1 D. 2 0
| |
| | |
| I REACTOR BUILDING AREA TEMPERATURES AREA INSTRUMENT MM MEMW AREA INSTRUMENT l mm MEM NORMAL SAFE ;NORMAL SAFE Ructor Buildine Pam14n5 Reacor Building r' st^
| |
| j
| |
| %9 t1 2.t2141 EL95, 61^tn)-D6 (ARTD-U6 MTI-lio uTiD6 104 *F 112*F 23hD21 4B2
| |
| '3RTDaCD 23-3 o'L%
| |
| j 104 *F l
| |
| j 153 *F 0unid "A' liPit onh 1114.1 Dowll j l IKIBa"'0 104 *F H3*F 3"''"" 33'2''3 ~ #"'93!
| |
| 120
| |
| * F 251 *F
| |
| """' ~t-l359 13RTD-1ti3. (33i2D, :09% j 66RTDJ 15 -
| |
| 13RTDan'D I Bdowrfca Pam14rti RCIC Dnvll Emranc 1.132 l. an9.. 120*F ilmr ahayi 3pg 104 *F 113*F 13RTDlo2A 132#B,u9% ,
| |
| 218 *F (ARU)-1" 13RTD-It'B l I
| |
| Outnde -B" Reacr Building !
| |
| 13,lBanen lPl nk gg,gop g33op 2"2 5W 2t30Aan95, j gggop j m op 0"m -y33n I
| |
| 23RTDoli 23-2"28, rL% : j MRTDJIn 23RTDolD !
| |
| I !
| |
| "A"RilR Ilar ! I 51.C Pamp Aru EPlinly 9 m op lxchangorr-m 23-2111A. m ,p I 242*F an95; l 3g4ep
| |
| %RTD114 i.159 23RTD"1A 23RTDolB 23-2nlB, arL%
| |
| 1' l
| |
| i
| |
| .-L--
| |
| Torus Rmm -
| |
| lil141 liPIC nh Suth IlPCI ,
| |
| Coling pemp N"1 MRU)-1li o.,m Al35-104 *F 133*F Stumlin 13RU)lart lWD - '
| |
| *9^*
| |
| in% l120*F l 280*F ;
| |
| 232.2 j 1
| |
| (
| |
| Torus Room -
| |
| Rucior Bui.ldine I.Pli nh0 SouhRCit 1121rA, an9m :
| |
| Minf NI, ARU)412 4 j 104 *F 158*F Stumlin g;g (3RTD-lCA ' ' '
| |
| 4pen l 120
| |
| *F j i
| |
| 280*F l 13RTD192B j J RWClIIa Paul 4rL21i '
| |
| I I
| |
| )
| |
| Panel'h-lixclunger l b#""' .
| |
| n e:
| |
| 12Ti.1Fl YS',Ps.3 115 *F 203*F ARTD-linB grg, 104*F 137 *F j gong >
| |
| 13T.4 IT 21St. Pv 3 j j
| |
| -B"RWCl' liandini2l pump rm IIPCI Rm jj 12T1(-11TTS2.Ps2 ! 135*F 225*F IHidlFD 2I181. P"s- 2 ! 23RTD'41 23-29JA. VL95. !
| |
| JrL%j 104*F *F j
| |
| 137 tFRW Cl' Pand d9-21 , 23RTD94B 23294B, pump room l *F 225F 23RTDllA 23-2FA, an95= I 12T1 IFA 21-52. Ps.l ! 125 '3RTD-1FB232FB,o9% j 12Tli-1FB21-St. Ps.I i r :
| |
| I Ructor h ftSW Buildine npp 4 g 104 *F 173*F RCIC R-m 13RTDwiA 3339 09% ' 104 g ,3, ;
| |
| j
| |
| *F t 137*F
| |
| %RU)-11I Al55; ggyp393 13-2A98. 1 "B" RitR ilu Wes1.rscm I I
| |
| i R "2 23RTD"2D B .
| |
| 130 *F 1
| |
| 242*F 13RTDT6A 13RTDhB @j.,)(' 104 *F j137 *F
| |
| | |
| Proposed Answer: B Explanation: EOP-5 entry isrequired duetoReactor Building ventilationexhaustradiation
| |
| (>1x103cpm), RCICDrywell entrance area temperature (>1200F), andReactor Building differentialpressure (at orabove 0"H20). EOP-6 entryisnotrequired, becausealthough Reactor Building exhaust radiation iselevated, there isnoindication provided thatthereisan off-site release rate above the alert level.
| |
| A. Incorrect -
| |
| NoEOP-6 entry conditionismetbythe given conditions. Plausible because there iselevated Reactor Building radiation andaloss ofnegative pressure, which will result insomeelevated release.
| |
| C.Incorrect -
| |
| Three EOP-5entry conditions aremet.Plausible ifanyofthethreegiven parameters are judged tonot be severe enough torequire EOPentry. NoEOP-6 entry condition ismetbythe given conditions. Plausiblebecause there iselevated Reactor Building radiation anda loss ofnegative pressure, which will insomeelevated result release.
| |
| D. Incorrect -
| |
| Three EOP-5 entryconditions are met.Plausible ifanyofthethreegiven parameters arejudged tonot besevere enough to require EOPentry.
| |
| Technical Reference(s): EOP-5, EOP-6, ARP-09-3-2-40, ARP-09-3-3-2(12)
| |
| Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11F 1.04,MIT-301.11G 6.05 Question Source: Bank 14-1 NRC#49 Question History: 14-1NRC#49 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES401 Written Examination QuestionWorksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 1 Group # 2 K/A# 295036 EA1.01 Importance Rating3.2 Secondary Containment High Sump/Area WaterLevel Ability tooperate and/ormonitor the asthey following apply toSECONDARY CONTAINMENT HIGHSUMP/AREA WATER LEVEL: Secondary containment equipment andfloor drain systems Proposed Question: #27 Given the followingconditions:
| |
| (1) Sumppumprun time istoolong (2) Time between pumpdowns istooshort (3) Sumplevel exceeds thehigh level setpoint Which oneofthe followingidentifies the that conditionsdirectly cause annunciator 09-4-1-39, RXBLDGEQUIP SUMPA LEAKAGE, toalarm?
| |
| A. 1and2,only B. 1and3,only C. 2and3,only D. 1,2 and3
| |
| | |
| Proposed Answer: A Explanation: There areonly twoconditions thatdirectly cause annunciator 09-4-1-39 toalarm.
| |
| They are either thesumppumprunning fortoolong during a single minutes) pumpdown(>8 or tooshort of a timer periodpassing between successive pumpdowns minutes).
| |
| (<55 B. Incorrect -
| |
| Sump level exceeding the highlevel setpoint causes annunciator RX 09-4-1-29, BLDGEQUIP SUMP A LVLHI, toalarm, does but notdirectly cause 09-4-1-39 annunciator toalarm. Toolong of asump pumpruntime also directly causes annunciator 09-4-1-39 to alarm.
| |
| C. Incorrect -
| |
| Sumplevelexceeding thehigh setpoint level causes annunciator RX 09-4-1-29, BLDGEQUIP SUMPA LVL HI, toalarm,but does notdirectly cause 09-4-1-39 annunciator toalarm. Tooshort ofatime between pumpdowns also directly annunciator causes 09-4 39toalarm.
| |
| D. Incorrect -
| |
| Sumplevel exceedingthe high level setpoint causes annunciator RX 09-4-1-29, BLDGEQUIP SUMPA LVLHI, toalarm, butdoes notdirectly causeannunciator 09-4-1-39 toalarm.
| |
| Technical Reference(s): ARPs09-4-1-39 and09-4-1-29 Proposed references tobeprovided toapplicantsduring examination: None Learning Objective: SDLP-20 1.12 Question Source: Bank 16-1 NRC#62 Question History: 16-1NRC#62 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(4)
| |
| Comments:
| |
| | |
| ES-401 Written Examination QuestionWorksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 203000K1.17 Importance Rating4.0 RHR/LPCl: Injection Mode Knowledge ofthephysical connections and/or relationships cause/effect between RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) andthe following:
| |
| Reactorpressure Proposed Question: #28 Theplant hasexperienced a loss ofcoolant accident the with following:
| |
| * Reactorwater level is70"andslowlylowering.
| |
| a Reactorpressure is445psig andslowlylowering.
| |
| a Drywellpressure is7.5psig andslowly rising.
| |
| Which oneofthe following describes thestatus ofRHR?
| |
| RHR...
| |
| A. iscurrentlyinjectingtothe Reactor.
| |
| B. remains inastandby lineup Reactor until water level reaches 59.5".
| |
| C. pumps have automatically started, butwill NOTinject until Reactor water level reaches 59.5".
| |
| D. pumps haveautomatically started, butwill NOTinject until Reactor pressurelowers further.
| |
| | |
| Proposed Answer: D Explanation: Reactorwater levelhasnotyetreached theLPCI initiation of59.5".
| |
| setpoint However, LPCI also initiatesonhigh Drywell pressure (>2.7 psig). RHR Therefore, pumps have started. With Reactor pressure <450 psig,the LPCI injection valves haveopened.RHRis not yet injecting to the Reactor because Reactor pressure isabove theshutoff headofthepumps.
| |
| Once Reactor pressure lowers below approximately 215psig, RHRwill begintoinject, regardless of current Reactor water level.
| |
| A. Incorrect -
| |
| RHRisnot injecting yet. Plausiblebecause pumps are andinjection running valves areopen.
| |
| B. incorrect -
| |
| RHRpumpsare running andinjection valves areopen. because Plausible Reactor water level is>59.5" C.Incorrect -
| |
| RHRwill when Reactor pressure lowers inject regardless ofReactor waterlevel.
| |
| Plausible because Reactor waterlevel is>59.5", which isanother LPCI signal.
| |
| initiation Technical Reference(s): OP-13, ARP 09-3-1-27, Simulator response Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-10 1.05.a.1.a(c)
| |
| Question Source: Bank SSESLOC26R NRC#17 (2015)
| |
| Question History: SSESLOC26R NRC#17(2015)
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(8)
| |
| Comments:
| |
| | |
| r ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 2 Group # 1 K/A# 205000 A1.01 importance Rating3.3 Shutdown Cooling Ability topredict and/or monitor changes associated inparameters operating with the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLINGMODE)controls including:
| |
| Heat exchanger cooling flow
| |
| | |
| Proposed Question: #29 A plant cooldown isinprogress with the following:
| |
| a RHR loop B isoperatinginShutdown Cooling mode.
| |
| a RHRSW pump B is running.
| |
| a RHRSWpump D is secured.
| |
| a 10MOV-89B, RHRSW DISCHVLVFROMHXB,isthrottled open.
| |
| a RHRSW loopB flow is 2500gpm.
| |
| * TheShift Manager has directed raising the cooldown rate.
| |
| Which oneofthe followingdescribes:
| |
| (1) the abilitytoraise the cooldown rate by raising RHRSW pumpB flow rate and (2) the abilitytoraise the cooldown rate bystarting RHRSW pumpD, inaccordance with OP-13D, RHR Shutdown Cooling?
| |
| M A. No No B. No Yes C. Yes No D. Yes Yes
| |
| | |
| Proposed Answer: D Explanation: Thegiven indications showRHRSWflow isnotmaximized (upto4000gpmper pumpisallowed, only currentlyat2500 gpmononepump). Therefore, thecooldown may rate beraised by further opening of 10MOV-89B toraise RHRSW pumpBflow. Additionally, the cooldown rate may beraised bystarting RHRSW pumpD.
| |
| A. Incorrect -
| |
| Thecooldown rate mayberaised byfurther opening of10MOV-89B toraise RHRSW pumpB flow. Plausible because RHRSWpumpBflow isintheallowable band, just low. RHRSWpump D isallowedtobestarted. Plausible that onlyonepumpwould be allowed tobeoperatedduring non-emergency conditions.
| |
| B.incorrect -
| |
| Thecooldownrate may beraised byfurther opening of10MOV-89B toraise RHRSW pumpBflow. Plausible because RHRSW pumpBflow isintheallowable band, just low.
| |
| C.Incorrect -
| |
| RHRSWpumpD is allowed tobestarted. Plausible thatonlyonepumpwould beallowed tobeoperated during non-emergency conditions.
| |
| Technical Reference(s): OP-13D Proposed references tobeprovided toapplicantsduring examination: None Learning Objective: SDLP-10 1.13.d Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(3)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 2 Group # 1 K/A# 205000 K3.02 Importance Rating3.2 Shutdown Cooling Knowledge oftheeffect that a loss ormalfunction of theSHUTDOWN COOLINGSYSTEM (RHR SHUTDOWN COOLING MODE) will haveonfollowing: Reactor water level:
| |
| Plant-Specific Proposed Question: #30 Theplant isshutdown with thefollowing:
| |
| * RHRloop B isoperating inShutdown Cooling mode.
| |
| * Reactorcoolant temperature is1200Fandslowly lowering.
| |
| Then, a significant leakfrom RHRpumpB suction flange results inthe following:
| |
| e Reactorwater level is210" andloweringslowly.
| |
| IfReactor water levelcontinues tolower,which oneofthe following identifies theReactor water levelwhich at anisolation signalwillfirst begenerated that willisolate the leak?
| |
| A. 196.5" B. 177.0" C. 126.5" D. 59.5"
| |
| | |
| I Proposed Answer: B Explanation: Thefirst isolation signal occursat177", which causes a SDCisolation (10MOV-17,-18,and -25B).
| |
| NA Thequestion meets the K/Abecause itpresents a malfunction ofSDC(systemleak) and requires the applicant to determine the effect onReactor water level oflevel (magnitude drop before anautomatic isolation signal isgenerated).
| |
| A. Incorrect -
| |
| Thefirstisolation signaloccurs at177"Plausible because isthe 196.5" setpoint for a Recirc runback.
| |
| C. Incorrect -
| |
| Thefirst isolation signal occurs at177". Plausible because126.5" isthesetpoint for HPCIandRCICstart.
| |
| D. Incorrect -
| |
| Thefirst isolation signal occurs at177". Plausible because59.5" isthe setpoint for LPCI initiationandGroup Iisolations.
| |
| Technical Reference(s): AOP-15 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-10 1.10.h Question Source: Bank NMP12018NRC#6 Question History: NMP12018NRC#6 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(9)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 206000 A1.06 Importance Rating3.8 High Pressure Coolant Injection Ability topredict and/or monitor changes inparameters associated with operating the HIGHPRESSURE COOLANT INJECTION SYSTEM controlsincluding:System flow Proposed Question: #31 Theplant isoperating at50%power with the following:
| |
| a ST-4N, HPCIQuick-Start, Inservice, and Transient isinprogress.
| |
| MonitoringTest, HPCIisrunning with its discharge aligned to the CSTs.
| |
| a HPCIflow andflow controller conditions areas shown inthe picturesonthefollowing page.
| |
| Then, the followingoccur:
| |
| * TheReactor scrams.
| |
| * Reactor water level lowers toa low of120inches.
| |
| Which oneofthe following describes theresulting operationofHPCl?
| |
| HPCIdischarge flow...
| |
| A. continues tobealigned tothe CSTsandiscontrolled bythe manual demand signal.
| |
| B. automatically re-aligns totheReactor andiscontrolled bythemanual demand signal.
| |
| C. continues tobealigned totheCSTsandautomatically controlsatapproximately4250 gpm.
| |
| D. automatically re-aligns tothe Reactor andautomatically controlsatapproximately 4250 gpm.
| |
| | |
| / [ . .
| |
| s
| |
| ,j i.,
| |
| $g 3
| |
| b.
| |
| HPCIFLOW CNTRL 230-1081 23RC108-1 71DC82
| |
| 'gg( ::..n.r..
| |
| a;-
| |
| a gy:3ocy;;
| |
| J::;;3j:::%
| |
| . l;:;
| |
| n$TVLV10 renov-ny,
| |
| | |
| Proposed Answer: B Explanation: Theinitialconditions showHPCIrunning with approximately 3400gpmtothe CSTsin manual flow control mode.Inthis alignment, 23MOV-21 and23MOV-24 areopento allow HPCI discharge flow togotothe CSTsand23MOV-19 isclosed toblockHPCIdischarge flow from going to the Reactor. WhenReactor water levellowers below126.5inches,HPCI receives anautomatic initiation signal. This causes 23MOV-21 and23MOV-24 tocloseand 23MOV-19 toopen. This shiftsall HPCIflow from theCSTstotheReactor. However,the HPCI flow controller doesNOT automatically shift intoautomatic onthelowReactor waterlevel signal, therefore HPCIflow control remains inmanual.
| |
| A. Incorrect -
| |
| TheHPCItest line isolates andthedischarge totheReactor automatically opens. Plausible becausethis istheinitial alignment andit does inmanual.
| |
| stay C. Incorrect -
| |
| TheHPCItest lineisolates and thedischarge totheReactor automatically opens. HPCIcontinues tooperate in manual flow controlmodeunless action operator is taken. Plausible because the initiallineup is tothe CSTs. Also that plausible theautomatic initiation signal would ensure design flow.
| |
| D. Incorrect -
| |
| HPCIcontinues tooperate inmanual flow control modeunless action operator is taken. Plausible that theautomatic initiation signal wouldensure designflow.
| |
| Technical Reference(s): ST-4N, OP-15,SDLP-23 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-23 1.05.c.4 and1.05.c.6 Question Source: Bank 14-2 NRC#17 Question History: 14-2 NRC#17 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(8)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 209001 K5.04 Importance Rating2.8 LowPressure CoreSpray Knowledge oftheoperational implications ofthefollowing concepts asthey apply to LOWPRESSURE CORESPRAY SYSTEM: Heat removal (transfer)mechanisms Proposed Question: #32 Theplant isoperating at100%power with the following:
| |
| Annunciator 09-3-1-1, CORESPRAYHDR A PIPEBREAKDETECTOR ALARM, alarms.
| |
| a Thealarm isdetermined tobeduetoa valid Core Spray line break.
| |
| Which oneofthe following identifies thelocation ofthe Core Spray linebreak?
| |
| A. Between thepumpandthe injection valve (14MOV-11A).
| |
| B. Between theinjection valve (14MOV-11A) andthe injectionlinecheck valve (14AOV-13A).
| |
| C. Between theinjection line check valve (14AOV-13A) andthe coreshroud.
| |
| D. Insidethe coreshroud.
| |
| | |
| Proposed Answer: C Explanation: This alarm iscaused bya change inpressure duetoa leak between theinjection line check valve, 14AOV-13A, andthe core shroud.
| |
| NoAThequestion meets the K/Abecause oneaspect ofthe Core Spray heatremoval mechanism isinjection through thesparger inside theCore Shroud. Thequestion an tests operational implication ofthis concept through thealarm andindications ofa breakthatwould cause injection tonotbe routed through the sparger, thereby affectingCore Spray's ability to properly remove heat from the fuel.Thequestion isnottesting the adequate corecooling concept ofSpray Cooling to avoid overlap with Question #90.
| |
| A. incorrect -
| |
| This alarm wouldnot detect a leak inthis location because both injection the valve andtheinjection line check valve prevent a pressure change here fromaffecting the leak detection instrument. Plausible because this leak location woulddisruptCoreSpray flow inthe samewayasa leak inthe correct location.
| |
| B. Incorrect -
| |
| This alarm would not detecta leak in this location because the line injection check valve prevents a pressure changehere from affecting the leakdetection instrument.
| |
| Plausible because thisleak location would disrupt Core Spray flow inthe samewayasa leak inthe correct location.
| |
| D.Incorrect -
| |
| This alarm would not detect aleak inthis location because therewouldbeno pressure change (thissection ofpiping isalready pressurized tothe samepressure as surrounding environment). Plausible because this section ofpiping is directly connected to thepiping that ismonitored bytheleak detection system.
| |
| Technical Reference(s): ARP09-3-1-1, FM-23A, SDLP-14 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-14 1.05.a.13 Question Source: Bank NMP22017Cert
| |
| #1 Question History:
| |
| Question Cognitive Level:MemoryorFundamental Knowledge 10CFRPart 55Content:55.41(8)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 211000A3.05 importance Rating4.1 Standby Liquid Control Ability tomonitor automatic operations oftheSTANDBY LIQUID CONTROL SYSTEM including: Flow indication:Plant-Specific Proposed Question: #33 Theplant hasexperienced afailure toscram with the following:
| |
| * Reactor power is15%.
| |
| * SRVsare cycling tocontrol Reactor pressure.
| |
| * TheStandby Liquid Control (SLC) keylock switch is takentoSTART SYSA.
| |
| Which oneofthe following describes anindication ofproperSLC flowtothe Reactor?
| |
| A. SLCpumpdischarge pressure of1175 psig.
| |
| B. SLCpumpdischarge pressure of1500 psig.
| |
| C. Squib circuit continuity meter reading 4 mA.
| |
| D. Squib circuit continuity meter reading 2A.
| |
| | |
| Proposed Answer: A Explanation: TheSRVswill control Reactor pressure ~1135 psig. WithSLCpumpdischarge pressureof 1175 psig, there isevidence ofproper flowtotheReactor.
| |
| Note: Whilethere isnodirect flowindication intheControl Room,Operators usedischarge pressure and squib indications todetermine the s tatusof flow. The questionmeetstheK/Aby testing this knowledge ofdischarge pressure andsquib indications todetermine the of status flow.
| |
| B.Incorrect -
| |
| A pressureof 1500 psig indicates thatthe explosive valves tofire failed andflow isthrough the reliefvalves back tothe SLCtank. Plausible because SLCpumps are positive displacement pumpsthat arecapableofproducing this pressureandthis pressure isabove Reactor pressure.
| |
| C.Incorrect -
| |
| This isnot indicationof proper squib firing,andtherefore indication notproper of flow tothe Reactor. Plausible because this is t henormal current through thesquibs.
| |
| D. Incorrect -
| |
| This isnotindication ofproper squib firing, andtherefore notproper indication of flow tothe Reactor. Plausible because this is the approximate firing for current thesquibs, but should goto0A upon successful firing.
| |
| Technical Reference(s): OP-17, SDLP-11 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-11 1.05.c.1 Question Source: Bank NMP12010 NRC#19 Question History: NMP12010NRC#19 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(6)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 212000 K4.02 Importance Rating3.5 Reactor Protection Knowledge ofREACTORPROTECTION SYSTEM design feature(s) interlocks and/or whichprovide for thefollowing: The prevention ofa reactor SCRAM asingle following component failure Proposed Question: #34 Theplant isoperatingat40%power whenTurbine Stop Valve (TSV) fully 3drifts closed.
| |
| Considering only theTurbine Stop Valve Closure scram signal, which oneofthefollowing describes theresulting operation oftheReactor Protection System (RPS)?
| |
| Based onthe Turbine Stop Valve Closurescram signal, ..
| |
| A. NOhalf scram signals occur.
| |
| B. a halfscram occurs onRPSA,only.
| |
| C. a halfscram occurs onRPSB,only.
| |
| D. afullscram occurs.
| |
| | |
| Proposed Answer: A Explanation: Each Turbine Stop Valve (TSV) hastwoposition switchesthat whenthe actuate valve isless than 90%open. These position switches inputtotheReactor System Protection scram circuitry. Thelogic isarranged such that somecombinations of2TSVscauseahalf but scram, TSVs 3 mustclose tocause anactual Reactor scram. Inthis TSV3 has case, drifted far enough to tripitsscram position but switches, nohalf scram without occur will another TSVdrifting.
| |
| B.Incorrect -
| |
| Nohalf scram is received. Plausible because TSV3hasdrifted farenough to trip its scram positionswitches.
| |
| C.Incorrect -
| |
| Nohalf scramis received. Plausible because TSV3 hasdrifted farenough to trip its scram positionswitches.
| |
| D. Incorrect -
| |
| A fullscram does not occur. Plausible because TSV3 hasdrifted enough far to trip its scram positionswitches.
| |
| Technical Reference(s):SDLP-05 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-94A 1.09.f Question Source: Modified Bank 16-1 NRC#10 Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| RPS Knowledge ofthe operational implications ofthe following concepts asthey apply to REACTOR PROTECTIONSYSTEM: Specific logic arrangements Proposed Question: #10 Theplant is operating at 40%power with thefollowing:
| |
| * Turbine Stop Valve (TSV) 4drifts 50%closed.
| |
| Then,TSV 3drifts50%dosed.
| |
| Considering only theTurbine Stop Valve Closure scram signal, which one following ofthe describes the resultingoperation of the Reactor Protection System?
| |
| Based onthe Turbine Stop Valve Closure scram signal, afull Reactor scram.
| |
| A. occurs while TSV4is drifting.
| |
| B occurs while TSV3is drifting C. does NOToccur because only thesetwoTSVs havedrifted.
| |
| D. does NOToccur because these twoTSVs have not tripped their scram position switches.
| |
| JAF16-1 NRC
| |
| | |
| ES-401 Written Examination QuestionWorksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 2 Group # 1 K/A# 215003 K2.01 Rating2.5 Importance Intermediate RangeMonitor Knowledge ofelectricalpower supplies tothe IRMchannels/detectors following:
| |
| Proposed Question:#35 Which oneofthe followingdescribesthe power tothe supply IRMdetectors?
| |
| A. 24VDCBattery Bus B. 125VDCBattery Bus C. 120VACUPSBus D. 120VACInstrument Bus
| |
| | |
| Proposed Answer: A Explanation: IRMdetectors arepower from the 24VDCBattery Buses.
| |
| B. Incorrect IRM detectors are power from the 24VDCBattery Plausible Buses. because this isanother possible DCsource.
| |
| C. Incorrect -
| |
| IRM detectors arepower from the 24VDCBattery Buses.
| |
| Plausible because this isthepower supply totheIRMrecorders anddetector drive control circuits.
| |
| D. Incorrect -
| |
| IRMdetectors arepower from the24VDCBattery Plausible Buses. because this isthe power supply tothedetectordrives.
| |
| Technical Reference(s): OP-16 Proposed references tobeprovided to applicants during examination: None Learning Objective: SDLP-07B 1.04.a Question Source: Bank17-1 NRC #26 Question History: 17-1NRC#26 Question CognitiveLevel:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(7)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier
| |
| # 2 Group# 1 K/A# 215003 A4.01 Rating3.3 Importance Intermediate RangeMonitor Ability tomanually operate and/or monitorinthecontrol room: IRMrecorder indication Proposed Question:#36 A plant isinprogress startup with thefollowing:
| |
| * TheReactor ModeSwitch isinSTART & HOTSTBY.
| |
| e IRMA indicates 85onRange 6.
| |
| Which oneofthe following describes IRMA iscausing a half scramandthe if required manipulation ofthe IRMA range switch, inaccordancewith OP-65, Startup Plant and Shutdown?
| |
| IRMA is...
| |
| A. causing a halfscram. Place IRMA onRange 5.
| |
| B. causing a halfscram. Place IRMA onRange 7.
| |
| C. NOTcausing a halfscram. Place IRMA onRange 5.
| |
| D. NOTcausing a halfscram. Place IRMA onRange 7.
| |
| | |
| I Proposed Answer: D Explanation: IRMA isnotcausing a halfscram because itisindicating IRMA
| |
| <118.5/125.
| |
| indication must beloweredback tothe range of5-75 per OP-65. This isaccomplished bygoing toRange 7.
| |
| A. incorrect -
| |
| IRM A is belowthe scramsetpoint of118.5. Plausible IRMA isabove because therange of5-75, and rightattheupscale rodblock setpoint. IRMA mustbetakento Range 7,not 5.Plausible because this isaneasily confused concept.
| |
| B. Incorrect -
| |
| IRMA isbelow thescram setpoint of118.5. Plausible IRMA isabove because the range of5-75, andright attheupscale rod block setpoint.
| |
| C.Incorrect -
| |
| IRMA must betaken toRange 7,not 5.Plausible because isaneasily this confused concept.
| |
| Technical Reference(s):ARP 09-5-2-52, OP-65 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-07B 1.05.a.4.f Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 215004A3.04 Importance Rating3.6 Source RangeMonitor Ability tomonitor automatic operations oftheSOURCE RANGEMONITOR (SRM)
| |
| SYSTEM including: Controlrod block status Proposed Question: #37 A plant startupisinprogress with the following:
| |
| * TheReactor ModeSwitch isinSTART & HOT STBY.
| |
| a AIIIRMsareonRange 1 a AllSRMsarepartially withdrawn.
| |
| * A malfunction ofthe SRMdrive control circuitry results in the indications:
| |
| following o SRMA:60cps o SRMB:130cps o SRMC:7 x 103 CpS o SRMD:3x 104 cps Which oneofthe following describes the status oftheSRMrodblock?
| |
| TheSRMrodblock is...
| |
| A. NOTreceived.
| |
| B. received duetoanSRMHiFlux signal.
| |
| C. received duetoanSRMDownscale signal.
| |
| D. received duetoanSRMDetector NotFull insignal.
| |
| | |
| Proposed Answer: D Explanation: TheSRMDetector NotFull Inrod block occurswhenanSRMisnotfully inserted with < 100 cps, associated IRMsonrange 1or2,andtheModeSwitch isnotinRUN.This prevents control rodwithdrawal with RMCSunder the given conditions duetoSRMA.
| |
| A. Incorrect -
| |
| A control rod withdrawal block isactive duetoSRMA being <100cpsand partially withdrawn. Plausible because this would becorrect ifSRMA were fully or inserted
| |
| >100 cps.
| |
| B. Incorrect -
| |
| SRMHiFlux rod blockoccurs with SRMcounts above 105cps. SRMsare All less than 105 cps. Plausible because SRMs B andD are indicating high.
| |
| fairly C.Incorrect -
| |
| SRMDownscale rod block occurs with SRMcounts at3cpsorless.
| |
| AIISRMs areabove 3cps. Plausible because SRMA iscausing a rod block because aretoo counts lowfor its position.
| |
| Technical Reference(s):OP-16, SDLP-07B Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-07B 1.05.c.1 Question Source: Bank14-1 NRC#5 Question History: 14-1 NRC#5 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 2 Group # 1 K/A# 2150052.1.28 ImportanceRating4.1 Average Power Range Monitor/Local Power RangeMonitor Knowledge ofthepurpose and function ofmajor systemcomponentsandcontrols.
| |
| Proposed Question: #38 Which oneofthe following describesthe way LPRMs are assigned APRMs?
| |
| tothe Each APRMreceives inputs from LPRMsin (1) -
| |
| core andfrom quadrants .- (2).
| |
| detector levels.
| |
| A. only 2 only 2 B. only 2 all 4 C. all4 only 2 D. all4 all 4
| |
| | |
| Proposed Answer: D Explanation: EachAPRMreceives LPRMinputs from all 4 core andall quadrants 4 detector levels.
| |
| A. Incorrect Each APRM receives LPRMinputs from all4 core andall quadrants 4 detector levels. Plausible because this would still provide averaging ofpower indifferent partsofthe core andwouldmake APRMs better atsensing uneven fluxdistribution.
| |
| B.Incorrect -
| |
| EachAPRM receives LPRMinputs from all4 core Plausible quadrants. because this would still provide averaging of power indifferent partsofthe andwould core make APRMsbetter atsensing uneven flux distribution.
| |
| C. Incorrect -
| |
| Each APRMreceives LPRM inputs from all4detector levels. because Plausible this would still provide averaging ofpower indifferent partsofthe andwould core make APRMsbetter atsensing uneven flux distribution.
| |
| Technical Reference(s): RAP 7.4.03, OP-16 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-07C 1.05.a.3.a Question Source: BankSSESLOC27NRC#7 (2015)
| |
| Question History: SSESLOC27 NRC#7(2015)
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 217000 A2.08 Importance Rating3.0 Reactor Coreisolation Cooling Ability COOLING (a) to predict SYSTEM theimpacts ofthefollowing (RCIC);and (b)basedonthose ontheREACTOR COREISOLATION useprocedures predictions, to correct, control, ormitigate the consequences ofthose abnormal conditionsor operations: Lossoflube oil cooling Proposed Question: #39 Theplant isoperatingat100%power withthe following:
| |
| RCICisbeing started for surveillance testing.
| |
| 13MOV-132, OILCLRWTRSUPP,fails closed.
| |
| a Thefollowing annunciators alarm:
| |
| o 09-4-1-5, RCICTURBCPLGENDBRGTEMP HI o 09-4-1-15, RCICTURBGOVENDBRGTEMPHI e Theassociated RCICturbine bearing temperatures are2000F slowly.
| |
| and rising Which oneofthe following describes:
| |
| (1) the coolingwater source that isblocked bythe failure of13MOV-132, and (2) therequired action, inaccordance with the Alarm Response Procedures?
| |
| A. (1)RBCLC (2)Manually trip RCIC B. (1)RBCLC (2)Verify automatic RCICtrip C. (1)RCICPumpDischarge (2)Manually trip RCIC D. (1) RCICPumpDischarge (2)Verify automatic RCICtrip
| |
| | |
| I Proposed Answer: C Explanation: 13MOV-132 supplies cooling water from theRCICpumpdischarge (~16gpm)to the RCIC oil cooler. RCICbearing high temperatures result incontrol but roomalarms, donot result inanautomatic trip ofRCIC. Theassociated alarm response procedures a require manual trip ofRCIC.
| |
| A. Incorrect -
| |
| 13MOV-132 supplies cooling water from theRCICpumpdischarge. Plausible because RBCLCsupplies coolingwater tomanyimportant loads Building.
| |
| intheReactor B.Incorrect -
| |
| 13MOV-132 supplies cooling water from theRCICpumpdischarge. Plausible because RBCLC supplies cooling water tomanyimportant loads inthe Building.
| |
| Reactor RCICdoes not automatically trip due tohigh bearing temperatures, butmustbemanually tripped. Plausible because this does cause analarm andRCIChasmanyautomatic trips.
| |
| D. Incorrect -
| |
| RCICdoesnotautomatically trip duetohigh bearing temperatures, butmustbe manually tripped. Plausible because this does cause analarm andRCIChasmany automatic trips.
| |
| Technical Reference(s): ARPs09-4-1-5, 09-4-1-15, OP-19, FM-22A Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-13 1.05.a.4 Question Source: Modified Bank16-1 NRC#86 Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(8)
| |
| Comments:
| |
| | |
| RCIC COOLING (a)
| |
| Abilityto predict SYSTEM the impacts (RCIC); and(b) ofthe following based onthose onthe REACTOR predictions, CORE ISOLATION useproceduresto correct, control, ormitigate the consequences ofthose abnormalconditions or operations: Loss oflube oil Proposed Question: #86 The plantis operating at100% power with the following:
| |
| * RHRpump A is inoperable for corrective maintenance.
| |
| * HPCI operability has been verifiedbyadministrative means.
| |
| * RCIC isbeing operated for surveillancetesting.
| |
| * A lube oilleak results in the followingannunciators alarming:
| |
| o 094-1-5, RCIC TURB CPLG END BRG TEMP HI o 09-4-1-15, RCIC TURB GOV ENDBRGTEMP HI o 094-1-25, RCICTURB OIL PRESS LO
| |
| * Theassociated RCIC turbine bearing temperatures are200*Fandrisingslowly.
| |
| * RCIC turbine oil pressure is2psig andstable.
| |
| Which oneofthe following describes:
| |
| (1) the required action, inaccordance with theAlarm Response Procedures,and (2) the mostlimiting applies asaresult Required ofthis Action event?
| |
| inTechnical Specification 3.5.3, (TS) RCICSystem, that A. (1) Direct manually tripping RCIC.
| |
| (2) BeinMode 3in12hours.
| |
| B. (1) Direct manually tripping RCIC.
| |
| (2) Restore RCIC tooperable status within 14days.
| |
| C. (1) Direct verification ofanautomatic RCIC trip.
| |
| (2) BeinMode3in12hours.
| |
| D. (1) Direct verification ofanautomatic RCIC trip.
| |
| (2) Restore RCIC tooperable status within 14days.
| |
| JAF16-1 NRC
| |
| | |
| ES-401 Examination Written Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 218000 K3.02 Importance Rating4.5 Automatic Depressurization Knowledge oftheeffectthat a lossormalfunctionoftheAUTOMATIC DEPRESSURizATION SYSTEM will have onfollowing: Abilitytorapidly depressurize the reactor Proposed Question: #40 Theplant wasoperating at100%power when the following events occurred:
| |
| a Anun-isolable Reactor Water Cleanup steam leakinto theReactor Building ledtothe need for anEmergency RPVDepressurization.
| |
| a Malfunctions have causedallseven (7)ADSSRVs tofail closed.
| |
| a MSIVs closed duetoaninvalid isolationsignal that has nowcleared.
| |
| a Main Condenser vacuum is20inches Hg.
| |
| a CWPumpA isinservice.
| |
| Which oneofthe following describes the effectthemalfunction oftheADS system hasonthe abilitytorapidly depressurize the inaccordance reactor, with EOP-2, RPV Control?
| |
| TheMinimum Number ofSRVsRequired for Emergency Depressurization [1) and Turbine Bypass Valves --(2) beused t orapidly depressurize theReactor.
| |
| (1) (2)
| |
| A. isavailable should B. isavailable should NOT C. isNOTavailable should D. isNOTavailable should NOT
| |
| | |
| Proposed Answer: C Explanation: Theplant has11SRVsandtheMinimum Number ofSRVsRequired for Emergency Depressurization is5.With 7 SRVsfailed closed duetoa malfunction oftheADS system, only 4 are available, which isless than therequired 5.With lessthan 5 SRVsopen, EOP-2 directs use ofGroup2 Pressure Control Systems torapidly depressurize theReactor.
| |
| Group 2 Pressure Control Systemsinclude Turbine Bypass Valves. Allowance isgiventore-open the MSlVs ifclosed andtooverride isolation signals ifpresent.
| |
| A. Incorrect -
| |
| TheMinimum Number ofSRVsRequired forEmergency Depressurization is5.
| |
| With 7 SRVsunavailable, only 4 remain available. Plausible because there arealmost enough SRVsavailable.
| |
| B.Incorrect -
| |
| TheMinimum Number of SRVsRequired forEmergency Depressurization is5.
| |
| With 7 SRVsunavailable, only4 remain available. Plausible because there arealmost enough SRVsavailable. EOP-2directs useofGroup 2Pressure ControlSystems torapidly depressurize the Reactor. Group 2 Pressure ControlSystems include Turbine Bypass Valves. Allowance isgiventore-openthe MSlVs if closed andtooverride signals isolation if present. Plausible because MSlVs are currently closed and enoughSRVsareopen to lower Reactor pressure rapidly.
| |
| fairly D. Incorrect -
| |
| EOP-2 directsuseofGroup 2 Pressure Control Systems torapidly depressurize theReactor. Group 2 Pressure ControlSystemsinclude Turbine Bypass Valves. Allowance isgiven tore-open theMSIVs ic flosed andtooverride isolation signalsifpresent. Plausible because MSlVs arecurrentlyclosed andenough SRVs are open tolower Reactor pressure fairly rapidly.
| |
| Technical Reference(s):EOP-2, MIT-301.11b Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11c 4.04 Question Source: Bank 16-1 NRC#6 Question History: 16-1 NRC#6 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A # 223002 K3.19 Importance Rating2.8 Primary Containment isolation/Nuclear Steam Supply Shutoff Knowledge oftheeffect that a loss ormalfunction of thePRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUTOFF will haveonfollowing:
| |
| Containment atmosphere sampling Proposed Question: #41 Theplant isoperatingat100%power when a malfunction causes a PCISGroup II isolation signal ononeDivision IIsub-channel.
| |
| Which oneofthefollowing describes theresultingstatus oftheH2/O2 monitors?
| |
| A. Both H2/O2 monitors remain un-isolated.
| |
| B. Both H2/O2 monitors isolate duetoclosure ofinboard isolation valves.
| |
| C. Both H2/O2 monitors isolate duetoclosure ofoutboard isolationvalves.
| |
| D. OneH2/O2 monitor isolates andoneH2/O2 monitorremains un-isolated.
| |
| | |
| Proposed Answer: A Explanation: PCISGroup IIhasa "2outof2 once" logic arrangement.ForH2/O2monitors, having both Division 11sub-channels activate inthe"B" results H2/O2 isolating monitor andthe "A" H2/O2monitor remaining inservice. With onlyoneDivisionIIsub-channel both activate, H2/O2 monitors remain in service.
| |
| B. Incorrect -
| |
| Both H2/O2 monitors remains un-isolated.
| |
| Plausiblebecause this wouldbe correct for mostPCIS Group II systems giventwoDivision failures.
| |
| II C.incorrect -
| |
| Both H2/O2 monitors remains Plausible un-isolated. because this wouldbe correct for mostPCISGroup II systems given twoDivision Ifailures.
| |
| D. Incorrect -
| |
| Both H2/O2 monitors remains un-isolated. Plausiblebecause would this be correct for twoDivisionII failures.
| |
| Technical Reference(s):SDLP-16C Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: SDLP-16C Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(9)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 239002 K6.05 importance Rating3.0 Safety ReliefValves Knowledge oftheeffect that a loss or malfunction ofthe following willhaveonthe RELIEF/SAFETY VALVES: Discharge line vacuumbreaker Proposed Question: #42 A plant transient resultsinthe following:
| |
| a SRVK opens duetohigh Reactor pressure andthen closes.
| |
| a AnSRVK vacuum breaker opens andsticks inthe open position.
| |
| Which oneofthe following describes theconsequence of the stuck open SRVvacuum breaker?
| |
| A. Steam will continue toflow fromtheReactor tothe Torusthrough the openSRVvacuum breaker.
| |
| B. IfSRVK opens again, someofthe steam passing through theSRV will bereleased directly tothe Reactor Building.
| |
| C. If SRVK opens again, someofthe steam passing through theSRVwill be released directly into the Torus airspace.
| |
| D. If SRVK opens again, someofthesteam passing through theSRVwill bereleased into directly theDrywell.
| |
| | |
| Proposed Answer: D Explanation: After SRVoperation, thevacuum breakers opentoequalize between pressure theDrywell and tailpipes. Without vacuum breaker operation, condensation ofsteaminthe tailpipe draws water from the Torus upinto the tailpipe.Uponsubsequent ofthe re-opening SRV,high forces would beexperienceddue totheclearing ofthe from water the extra tailpipe.
| |
| With astuck open vacuum breaker, subsequent SRVopening would admitsteamdirectly tothe Drywell airspace, resulting in rising Drywell temperature andpressure.
| |
| A. Incorrect -
| |
| Theclosed SRV isolates the vacuum breaker from Thevacuum theReactor.
| |
| breaker is connected b etween the SRV discharge pipingand the air Drywell space, notthe Reactor. Plausible because this is theanswer that would bechosen the if vacuum breaker connected back totheReactor, which would functiontobreak vacuumintheSRVdischarge piping.
| |
| B. Incorrect -
| |
| TheSRVtailpipe vacuum breakers connect tothe Drywell notReactor airspace, Building. Plausible because this isthe answer that would bechosen if thevacuum breaker connected tothe Reactor Building airspace, which would function tobreakvacuum inthe SRVdischarge piping.
| |
| C.Incorrect -
| |
| TheSRVtailpipe vacuum breakers connect to theDrywell airspace, notTorus.
| |
| Plausible because this isthe answer that would be chosen if the vacuumbreaker connected tothe Torus airspace, which would function tobreak vacuum inthe SRVdischarge piping.
| |
| Technical Reference(s): SDLP-02J Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-02J 1.09.f Question Source: Bank 16-1 NRC#26 Question History: 16-1 NRC#26 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(7)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 2 Group # 1 K/A# 259002 K1.16 Importance Rating3.4 Reactor Level Control Water Knowledge ofthephysical connections and/or cause-effect relationships between REACTOR WATERLEVELCONTROL SYSTEMandthe following: HPCI: PlantSpecific Proposed Question:#43 Which oneofthe followingidentifies theReactor water level instrumentation that isusedfor automatic initiation andtripping ofHPCI?
| |
| A. Widerange levelinstruments areused both of for thesefunctions.
| |
| B. Narrowrange levelinstruments are used for both of these functions.
| |
| C. Wide range levelinstruments areused automatic for initiation andnarrow rangelevel instrumentsareused forthehigh level trip.
| |
| D. Narrowrange levelinstruments are used for automatic initiation and widerangelevel instrumentsareused forthehigh level trip.
| |
| | |
| Proposed Answer: C Explanation: HPCIautomatic initiation uses wide range level 02-3LT-transmitters 72A(B)(C)(D). HPCIhigh level tripuses narrow rangelevel 02-3LT-83C(D).
| |
| transmitters A. Incorrect HPCI high level tripuses narrow rangeleveltransmitters.
| |
| Plausible because wide range is used for manyother functions, includingtheHPCIautomaticinitiation.
| |
| B. Incorrect -
| |
| HPCI automatic uses initiation wide range transmitters.
| |
| level Plausible because narrow range isused formanyother functions, includingtheHPCIhigh trip.
| |
| level D.Incorrect -
| |
| HPCIautomatic initiation uses wide range level transmitters.
| |
| Plausible because narrow range isused for many other functions, includingtheHPCIhigh level trip.
| |
| HPCIhigh level tripuses narrow range level transmitters. Plausiblebecause widerange isused for manyother functions, including the HPCIautomatic initiation.
| |
| Technical Reference(s):SDLP-02B Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-02B 1.05.c Question Source: New Question History:
| |
| Question CognitiveLevel:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(8)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 261000 A3.01 Importance Rating3.2 Standby GasTreatment Ability tomonitor automatic operations oftheSTANDBY GASTREATMENT SYSTEM including: System flow Proposed Question: #44 Theplant isoperating at100%power with the following:
| |
| * Annunciator 09-3-2-40, RX BLDGVENT RAD MONHI-HI, isreceived.
| |
| * Reactor Building Ventilation exhaust radiation monitors indicate:
| |
| o 17RM-452A: 3x 104 cpm o 17RM-452B: 5x 103 epm Which oneofthefollowing describes the status oftheStandby Gas Treatment (SGT) system?
| |
| A. Both trainsofSGTremain instandby.
| |
| B. SGTtrain A auto-initiates. SGTtrain B remains instandby.
| |
| C. SGTtrain B auto-initiates.SGTtrain A remains instandby.
| |
| D. Both trainsofSGTauto-initiate.
| |
| | |
| Proposed Answer: B Explanation: 17RM-452A isabove thehi-hi setpoint of1x 104 cpmand17RM-452B isbelow the hi-hisetpoint. Eachofthese radiation monitors causes auto-initiationoftheir respective SGTtrain when above the hi-hi setpoint. Therefore, only SGTtrain andSGT A auto-initiates train B remains in standby.
| |
| A. Incorrect -
| |
| SGT train A auto-initiates duetohi-hi radiation. Plausible becauseonly asingle instrument isabove the hi-hisetpoint.
| |
| C.Incorrect -
| |
| SGTtrain B remains instandby. SGTtrain A auto-initiatesduetohi-hi radiation.
| |
| Plausible that there would be adistinction between above andbelow refuel floor radiation monitors andwhich train automatically starts (the given monitors arebelow floor).
| |
| refuel D.Incorrect -
| |
| SGTtrain B remains instandby. Plausible because instrument a single above hi-hi does cause aninitiation.
| |
| Technical Reference(s): ARP 09-3-2-40, OP-20, AOP-15, SDLP-01B Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-01B 1.05.c.1 Question Source: Bank14-1 NRC#7 Question History: 14-1 NRC#7 Question Cognitive Level:Comprehension orAnalysis 10C'FR Part 55Content:55.41(9)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 261000 2.1.30 Importance Rating4.4 Standby GasTreatment Ability tolocate andoperate components, including localcontrols.
| |
| Proposed Question: #45 Theplant hasexperienced asteam leak inthe ReactorBuilding with the following:
| |
| a Standby GasTreatment (SBGT) train A is inservice.
| |
| a Annunciator 09-75-1-16, SGTSYSA ACT CHAR TEMPHI, alarms.
| |
| a Anoperator inthe field hasconfirmed that there is anactivefire intheSBGTtrain A charcoal filter.
| |
| a Initiation offire suppression from the Fire Protection Panel has failed.
| |
| a TheUnit Supervisor hasdirected initiationoffiresuppression tothe SBGTtrain A charcoalfilteratthelocal breakglass station.
| |
| Which oneofthe followingdescribes themethod offire suppression that istobeinitiated and thelocation ofthe localbreakglass station?
| |
| M A. Water Reactor el.
| |
| Building 272' B. Water Reactor Building el. 300' C. CO2 Reactor Building el. 272' D. CO2 Reactor Building el. 300'
| |
| | |
| Proposed Answer: A Explanation: Themethod offire suppression tothe SBGTtrain A charcoalfilter iswater spray.
| |
| Thelocal breakglass station islocated onthesouth wall ofReactor Building272' el.
| |
| B.Incorrect The localbreakglass station islocatedonthe south wall ofReactor Building el.
| |
| 272'. Plausible because this isa valid Reactor Building elevation thatdoes SBGT-contain related components (flow instrumentation).
| |
| C.Incorrect -
| |
| Themethod offire suppression tothe SBGTtrain A charcoal filter is spray.
| |
| water Plausible because introduction ofwater toacharcoal filtercaninitiateanundesirable exothermic reaction.
| |
| D. incorrect -
| |
| Themethod of fire suppression totheSBGTtrain A charcoal filter spray.
| |
| iswater Plausible because introduction ofwater toacharcoal filtercaninitiateanundesirable exothermic reaction. Thelocal breakglass station islocated onthe south ofReactor wall Building el. 272'. Plausible because this is avalid Reactor Building that elevation does contain SBGT-related components (flow instrumentation).
| |
| Technical Reference(s):OP-20,SDLP-01B Proposed references tobeprovided toapplicantsduring examination: None Learning Objective: SDLP-01B 1.08.c Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(9)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 262001 A4.01 importance Rating3.4 ACElectrical Distribution Ability tomanually operate and/or monitor inthecontrol room: All breakers and disconnects (including available switch yard): PlantSpecific Proposed Question: #46 Theplant isoperating at22%power with the following:
| |
| * TheMain Generator isconnected tothe grid through both output breakers.
| |
| * Then, aMain Turbine tripoccurs.
| |
| Which oneofthe following describes the resulting status of the Main Generator breakers, output 71PCB-10042 and71PCB-10052, anddisconnect 70MOD-10031 three(3) minutes later?
| |
| Output Breakers Disconnect 71PCB-10042 and71PCB-10052 70MOD-10031 A. Open Open B. Open Closed C. Closed Open D. Closed Closed
| |
| | |
| Proposed Answer: A Explanation: Both Main Generator output breakers automatically openontheMain Turbine trip. Both output breakers remain open until manual action istaken toreclose them.Main Generatordisconnect 70MOD-10031 also automatically opens onthe Main Turbine trip70MOD-10031 also remains open unless manual action istaken.
| |
| B.Incorrect -
| |
| Main Generator disconnect70MOD-10031 automatically opensontheMain Turbine trip. Plausible thatthis would remain closed untilmanual action istaken, asthe Main Generator output breakers openandremain openontheMain trip.
| |
| Turbine C.Incorrect -
| |
| Both Main Generator output breakers automatically openontheMain Turbine trip andremain open untilmanual actionis taken toreclose them. Plausible they that would automatically re-close after disconnect(s) open t o re-establishthe preferred 345KVelectrical distribution system alignment.OP-11A does contain manuai actionstoreclose these breakers for this reason. Main Generator disconnect 70MOD-10031 automatically opens on the Main Turbine trip.Plausible thatthis would remain closed untilmanual is action taken, astheMain Generator output breakersopen andremain open ontheMain Turbine trip.
| |
| D.Incorrect -
| |
| Both Main Generator output breakers automatically open ontheMainTurbine trip andremain open untilmanual action istaken toreclose them. Plausible they that would automatically re-close after disconnect(s) opento re-establish the 345KV preferred electrical distribution system alignment. OP-11A does contain manual actions toreclose these breakers for this reason.
| |
| Technical Reference(s): AOP-2, OP-11A Section F Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-71C 1.05.b.1 Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(4)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 262002 A2.02 Importance Rating2.5 Uninterruptable Power Supply (AC/DC)
| |
| Ability SUPPLY (a) to predict theimpacts ofthe (A.C./D.C.);
| |
| following and(b) based onthose ontheUNINTERRUPTABLE predictions, useprocedures POWER tocorrect, control, ormitigate theconsequences ofthose abnormal conditions Over oroperations:
| |
| voltage Proposed Question: #47 Theplant isoperating at100%power withthe following:
| |
| = A malfunction occurs intheRPSMGSetB voltage regulator.
| |
| * Annunciator 09-5-1-15, RPSMGB TROUBLE, alarms.
| |
| * Outputvoltage from RPSMGSetB rises to150 VAC.
| |
| Voltagestays atthisvalue for 10seconds andthen lowers back tonormal.
| |
| Which oneofthe following describes theimpact ofthis voltage transient onRPSandtheneed toenter AOP-60, Loss ofRPSBusB Power?
| |
| impact onRPS A. EPAstrip Required B. EPAstrip NOTrequired C. Transferstoalternate power Required D. Transferstoalternate power NOTrequired
| |
| | |
| Proposed Answer: A Explanation: With RPSMGSetoutput voltage >132VACfor >4seconds, theovervoltage trip ofthe EPAs occurs. This results inloss ofpower toRPSB,which requires into entry AOP-60.
| |
| B. Incorrect AOP-60 entry isrequired. Plausible MGSetoutput because voltage quickly returns tonormal.
| |
| C. Incorrect -
| |
| EPAs trip. Plausible because RPSdoes have power analternate source capable ofpowering the buses.
| |
| D.Incorrect -
| |
| EPAstrip. Plausible because RPSdoes have power analternate source capable ofpowering the buses. AOP-60entry isrequired.
| |
| Plausible becauseMGSet output voltage quicklyreturns tonormal.
| |
| Technical Reference(s): ARP 09-5-1-15, AOP-60 Proposed references tobeprovided toapplicants duringexamination:None Learning Objective: SDLP-05 1.14.a Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 263000K2.01 Importance Rating3.1 DCElectrical Distribution Knowledge ofelectricalpower supplies tothe following:
| |
| MajorD.C.loads Proposed Question: #48 Theplant isoperating at100%power when 125VDCBattery BusA de-energizes duetoa sustained electrical fault.
| |
| Which oneofthe following automaticallytransfers toDCPower loads B?
| |
| System A. ADSA Control Power B. HPCI A Control Power C. EDGA andC Control Power D. Core Spray A ControlPower
| |
| | |
| Proposed Answer: A Explanation: Ona lossofDCPower System A,ADSA control power transfers automatically to DCPower System B.
| |
| B. Incorrect HPCI A control power does nottransfer toDCPower System B.Plausible because DC Power System A isthepower supply, someloads doautomatically transfer, andHPCIisan important load.
| |
| C.Incorrect -
| |
| EDGA and C controlpower doesnottransfer toDCPower System B.Plausible because DCPowerSystem A isthe power supply, someloads doautomatically transfer, andEDGsA andC areimportant loads.
| |
| D.Incorrect -
| |
| CoreSprayA control powerdoes not transfer toDCPower System B.Plausible because DCPower SystemA is thepowersupply, someloads doautomatically transfer, andCore A isanimportant load.
| |
| Spray Technical Reference(s): AOP-45 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-71B 1.09.a.1,3, 6, and13 Question Source: Modified Bank 14-1 NRC #23 Question History:
| |
| Question CognitiveLevel:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(8)
| |
| Comments:
| |
| | |
| DCElectrical Distribution Ablilty tomonitor automatic operations oftheD.C.ELECTRICALDISTRIBUTION including: Meters, dials,recorders, andindicating alarms, lights Proposed Question: #23 The plant isoperating at100%power whenthefollowing annunciators alarm:
| |
| * 09-8-1-22, 125VDC BATTCHGRBACSUPPTROUBLE
| |
| * 09-8-1-23, 125VDCBATTBVOLTLO 125VDCBATT BUS B meter onPanel 09-8 OVDC.
| |
| indicates Which ofthefollowing automatic occurs operations asaresult ofthese conditions?
| |
| (1) ADSLogic Btransfersto DC Power System A (2) RCICLogic Btransfers to DC Power SystemA (3) HPCILogic Btransfers toDC Power SystemA A (1) only B. (2) only C. (3) only D. (1), (2), and(3)
| |
| | |
| ES-401 Written Examination Worksheet Question FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier
| |
| # 2 Group# 1 K/A# 264000 K6.08 Rating3.6 importance Emergency Generators (Diesel/Jet) EDG Knowledge oftheeffectthat a lossormalfunctionofthefollowinghaveonthe will EMERGENCY GENERATORS (DIESEL/JET): A.C. power
| |
| | |
| Proposed Question: #49 Theplant isoperating at100%power withthe following:
| |
| * Bus 10300 NormalSupply Breaker 10302 trips.
| |
| a Bus10300 Reserve Supply Breaker 10312 isopen andremains open.
| |
| * Thefollowing picture shows thestatus ofEmergency Diesel Generator (EDG) A andC output andtie breakers oneminute later:
| |
| .' magam ihEDdd y f@g; Aw s
| |
| o
| |
| @) #g m, g @P .
| |
| pj in AEL
| |
| ! 2 x
| |
| : 4. % m
| |
| , , A
| |
| , [
| |
| 1x w x p
| |
| 2 A j@
| |
| Which oneofthe following describes the status ofthese breakers?
| |
| A. AIIthree breakers areinthe correct position.
| |
| B. Theoutput breakers areinthecorrect position, but the tiebreaker isNOTinthecorrect position.
| |
| C. Thetie breaker isinthe correct position, but theoutput breakers areNOTinthecorrect position.
| |
| D. NONE ofthe breakers areinthe correct position.
| |
| | |
| Proposed Answer: B Explanation: Whenbreaker 10302 tripswith nofaultonthe10300 bus, breaker10312 should close to re-energize the10300 bus. Since 10312 isopenandremains open,the10300 busde-energizes. This alsocauses the10500 bustode-energize. Undervoltage onthe 10500bus should cause EDGs A andC tostart, their output breakers toclose, andtheir tie breaker to open. Thepicture shows theoutput breakers closedas expected, butthe breaker t ie failed to open asexpected.
| |
| A. Incorrect -
| |
| Thetie breaker should beopen because the EDGsstarted duetoundervoltage.
| |
| Plausible because thetie breaker is normally closedinthe standby lineup.
| |
| C.Incorrect -
| |
| Theoutput breakers should beclosed because stemconditions resulted in undervoltage onthe10500bus. Thetie breakershould beopen becausetheEDGsstarted duetoundervoltage. Plausible because this would becorrect for aLOCAstart EDGs ofthe without undervoltage.
| |
| D. Incorrect -
| |
| Theoutput breakers should beclosed because stem conditions resulted in undervoltage onthe10500 bus. Plausible that thetripof10302 than (rather undervoltage onthe busalone) would prevent automatic EDG loading.
| |
| Technical Reference(s): OP-22 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-93 1.05.b.3 Question Source: Bank 14-2 NRC#48 Question History: 14-2 NRC#48 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(8)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A # 264000 K5.05 Importance Rating3.4 Emergency Generators (Diesel/Jet) EDG Knowledge oftheoperational implications ofthefollowing concepts astheyapplyto EMERGENCY GENERATORS (DIESEL/JET): Paralleling A.C. power sources Proposed Question: #50 Theplant isoperating at100%power with the following:
| |
| a Theregular monthly startandIoad test is being performed for EDGsA andC perST-9BA,EDGA andC Full Load Test andESW Pump Operability Test.
| |
| Which oneofthe following describes howEDGsA andC and the10500 busareoperated during the loaded portionofthis test?
| |
| EDGA andC areoperated with their governors in...
| |
| A DROOP mode. The10500 busisdisconnected from the10300bus.
| |
| B. DROOP mode. The10500 busremains connected tothe10300 bus.
| |
| C. NORMAL mode. The10500 busisdisconnected from the10300 bus.
| |
| D. NORMAL mode. The10500 busremains connected tothe10300 bus.
| |
| | |
| Proposed Answer: B Explanation: Before theEDGsareparalleled tothe10500 bus, their areplaced governors in DROOP mode toensureproper load sharing.During the loaded ofthe portion the10500 test, busremains connected tothe 10300 bus.
| |
| A. incorrectDuring theloaded portion ofthe the10500 test, busremains connected tothe 10300 bus. Plausible because the 10300and10500 buses whentheEDGs disconnect auto-start onUV.
| |
| C.Incorrect -
| |
| Before the EDGs are paralleled tothe10500 bus, governors their are in placed DROOP modetoensure proper load Plausible sharing. because standby conditions have the EDGsinNORMAL. During the loadedportionofthe test, the10500busremains connected tothe 10300 bus. Plausible because the 10300 and10500 busesdisconnect whentheEDGsauto-start onUV.
| |
| D.Incorrect -
| |
| Before theEDGsareparalleled tothe10500 bus, their areplaced governors in DROOP toensure m ode proper sharing.
| |
| load Plausible because standby conditions have the EDGsinNORMAL.
| |
| Technical Reference(s): ST-9BA Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-93 1.15.a Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(10)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 300000 K4.03 Importance Rating 2.8 Instrument Air Knowledge ofINSTRUMENT AIR SYSTEM design feature(s) andorinterlocks which provide for thefollowing: Securing ofIASuponloss ofcooling water Proposed Question: #51 Theplant isoperatingat100%power with the following:
| |
| * AirCompressor B isrunning.
| |
| * Then, coolingwater flow toAir Compressor B islost.
| |
| Which oneofthe followingdescribes the system that supplies Air Compressor Bwith cooling water andthe signal thatwilltrip Air Compressor B?
| |
| A. RBCLC Lowcooling water flow B. RBCLC Highairoroiltemperature C. TBCLC Lowcooling water flow D. TBCLC Highairoroiltemperature
| |
| | |
| Proposed Answer: D Explanation: Air Compressor B is supplied cooling water from TBCLC. Compressor Air B has trips onhigh airandoil temperatures, which willresult from a loss ofTBCLCflow, butnota direct trip on low TBCLC flow.
| |
| A. Incorrect -
| |
| Air Compressor B issupplied cooling water from TBCLC.Plausible becauseAir Compressor B supplies air tomanycomponents intheReactor Air Building. CompressorB hastrips onhighair and oil temperatures, but not adirect trip onlow TBCLCflow.Plausible because flow automatically initiates oncompressor andloss start, offlow lead will toatrip.
| |
| B. Incorrect -
| |
| Air Compressor B issupplied cooling water from TBCLC.Plausible becauseAir Compressor B supplies air to many components intheReactor Building.
| |
| C.incorrect -
| |
| Air CompressorB has tripsonhigh air andoil temperatures, butnotadirecttrip onlowTBCLC flow. Plausiblebecause flow automatically initiates oncompressor and start, loss offlow will lead toatrip.
| |
| Technical Reference(s):OP-39, ARP 09-6-2-18 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-39 1.05.c.3 Question Source: Bank NMP12013Cert
| |
| #52 Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(4)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 300000 2.4.49 Importance Rating4.6 Instrument Air Ability toperform without reference toprocedures those that actions require immediate operation ofsystem components andcontrols.
| |
| Proposed Question: #52 Theplant isoperatingat100%power with the following:
| |
| Anair leak develops intheReactor Building.
| |
| Operators have located theleak andare attempting toisolateit.
| |
| Instrument Airheader pressure is95psigand stable.
| |
| Scram Air header pressure is58psig andstable.
| |
| a Annunciator 09-5-2-3, RODDRIFT, isinalarm.
| |
| a Onecontrol rod hasdrifted infrom position 12to00.
| |
| NOother control rods have drifted.
| |
| Which oneofthe following describes thecurrent need for a manual Reactor scram, in accordance AOP-12, with Loss ofInstrument Air, andAOP27,ControlRod Drift?
| |
| A. Both ofthese AOPscurrently require a manual scram.
| |
| Reactor B. AOP-12 currentlyrequires a manual Reactor scram, AOP-27 but does NOT.
| |
| C. AOP-27 currentlyrequires a manual Reactor scram, AOP-12 but doesNOT.
| |
| D. NEITHER ofthese AOPscurrently requires a manual scram.
| |
| Reactor
| |
| | |
| Proposed Answer: B Explanation: AOP-12entry isrequired duetolowering airpressures. AOP-27 isrequired entry duetothe control rod drift. TheOverride ofAOP-12 requires a manual Reactor scramdueto the singlecontrol rod drift. AOP-27 does notcurrently require a manual Reactor but scram, would if a second control rod drifted.
| |
| A. Incorrect -
| |
| AOP-27 does not currently require a manual Reactor scram.Plausible because it would if asecond control rod drifted.
| |
| C. Incorrect -
| |
| AOP-27does notcurrently require a manual Reactor scram.Plausible because would it if a second control roddrifted.AOP-12 does require a manualReactor scram.
| |
| Plausible because air pressures arestable, Operators arestill corrective attempting action, andonly onerod hasdrifted.
| |
| D. Incorrect -
| |
| AOP-12 does require a manual Reactor scram. Plausible because air pressures arestable, Operators are stillattempting corrective action,andonly onerodhasdrifted.
| |
| Technical Reference(s): AOP-12, AOP-27 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-39 1.15.a Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 1 K/A# 400000 K6.05 Importance Rating2.8 Component Cooling Water Knowledge oftheeffectthat a lossormalfunctionofthefollowing willhave onthe CCWS:Motors Proposed Question: #53 Theplant isoperatingat100%power with the following:
| |
| = RBCLC pumpsA andB arerunning.
| |
| a RBCLC pumpC istagged outfor maintenance.
| |
| Then, RBCLC pumpA trips onmotor overcurrent. RBCLC pump B trips onmotorovercurrent oneminute later.
| |
| Which oneofthe following describes theresponse oftheEmergency Service Water (ESW) system, ifany,andtheneed for a manual Reactor scram, inaccordance withAOP-11,Loss of Reactor Building Closed LoopCooling?
| |
| A. ESWremains instandby. A manual Reactor scramisrequired.
| |
| B. ESWremains instandby. A manual Reactor scramisNOTrequired.
| |
| C. ESWautomatically startsandinjects into theRBCLCsystem. A manual Reactor scram isrequired.
| |
| D. ESWautomatically startsandinjects into theRBCLCsystem. A manual Reactor scram isNOTrequired.
| |
| | |
| Proposed Answer: C Explanation: With RBCLCpumpCtagged outandboth RBCLCpumpA andB tripped, RBCLCpressure will lower below 40psig. Thiscauses ESWtoautomatically into inject RBCLC. A manual scramisrequired byAOP-11 duetotrip ofall RBCLC pumps.
| |
| A. Incorrect -
| |
| With no RBCLC pumps running, RBCLCpressure lowers below40psig.
| |
| This causes ESWtoautomatically inject into RBCLC.Plausible because ESWdoes not automatically start based onRBCLC pumptrips alone.
| |
| B.Incorrect -
| |
| With noRBCLC pumps running, RBCLC pressure lowers below40psig.
| |
| This causes ESWtoautomatically injectinto RBCLC.Plausible because ESWdoesnot automatically start basedon RBCLC pumptrips alone. A manual isrequired scram byAOP-11duetotrip ofall RBCLCpumps. Plausible that anemergency reduction power would first beperformed andequipment temperatures monitored before requiring ascram.
| |
| D. Incorrect -
| |
| A manual scram isrequired byAOP-11 duetotrip RBCLCpumps.
| |
| ofall Plausible that anemergency powerreduction would beperformed first andequipment temperatures monitored before requiring a scram.
| |
| Technical Reference(s):AOP-11 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-15 1.05.c.5 and1.15.a Question Source: Bank 14-1 NRC#11 Question History: 14-1 NRC#11 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(4)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 2 K/A# 2010012.2.12 Importance Rating3.7 CRDHydraulic Knowledge ofsurveillance procedures.
| |
| Proposed Question: #54 Theplant isoperating at100%powerwith thefollowing:
| |
| a Monthly surveillance test ST-20C, Control RodOperability forFully Withdrawn Control Rods, isbeing performed.
| |
| Which oneofthe following describes thegeneral testmethod used inthis test?
| |
| Eachtested controlrodis...
| |
| A. determined tobeoperable byadministrative means only.
| |
| B. kept atposition 48while acouplingcheck isperformed.
| |
| C. insertedonenotch andthen returned toposition 48.NOcoupling check isrequired.
| |
| D. insertedonenotch andthen withdrawn toposition48while performingacoupling check.
| |
| | |
| Proposed Answer: D Explanation: ST-20Cboth exercises the control rodbyinsertingit andthen onenotch, returning it to position 48while performing acouplingcheck.
| |
| A. incorrect Each control rod ismovedonenotch anda coupling isperformed.
| |
| test Plausible because control rods are checked byonly meansinST-40D.
| |
| administrative B. Incorrect -
| |
| Thecontrol rodisalso movedonenotch. Plausible the that control rod would not bemoved tominimize unnecessary reactivity changes.
| |
| C. Incorrect -
| |
| A coupling check is alsoperformed. Plausibleacoupling checkwasalready performed onthe rodwhen it wasinitially at48,anduncoupling positioned while stationary atposition 48ishighly unlikely.
| |
| Technical Reference(s): ST-20C Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: SDLP-03C 1.13.j Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(6)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 2 K/A# 201003 A1.03 ImportanceRating2.9 Control RodandDrive Mechanism Ability topredict and/ormonitor changes inparametersassociated with operating the CONTROL RODANDDRIVE MECHANISM including:
| |
| controls CRDdrive waterflow Proposed Question: #55 A plant startupisinprogress with the following:
| |
| a Anoperator attempts tonotch withdraw control rod 22-07 from position 08to10.
| |
| * Drivewater flow indicates initially 4 gpmand the control rodmoves intothecore as expected for acontrol rod withdrawal.
| |
| a Then, drivewater flow becomes 0 gpmandthe control rod settles atposition 08.
| |
| Which oneofthe following solenoid operated directional control valve failures wouldcause the observed indications?
| |
| Directional controlvalve.
| |
| A. 120, WITHDRAW EXHAUST ANDSETTLE VALVE, stuck open B. 121, INSERTEXHAUST VALVE, stuck open C. 122, WITHDRAW SUPPLY VALVE,stuck closed D. 123, INSERTSUPPLYVALVE,stuck closed
| |
| | |
| Proposed Answer: C Explanation: Whenthe rodmovement control switch ismoved totheRODOUTposition, the RMCStimer opens theinlet drive water valve (123) andthe exhaust valve (121) andthecontrol rodmovesinto thecore andoff thecollet fingers. RMCSthen should open thewithdrawvalve (122) and exhaust valve (120). Ift he w ithdraw valve (122) does N OT open n opressureis applied tothecollet fingers orthe area above thedrive pistonthe controlrodwillsettle back onto thecollet finger at itsoriginal position. This isfurther indicated bythe0.0 gpmdrivewater flow.
| |
| A. Incorrect -
| |
| If120wasstuck open, the control rod would notinsert asdrive initially, water flow through 123 would flow directly to the e xhaust header through o the pen 1 20.
| |
| B. Incorrect -
| |
| If121wasstuckopen, the control rod would not withdraw, butdrivewaterflow would indicate high since drivewater would flow directly through 122tothe exhaustheader through the open121.
| |
| D. Incorrect -
| |
| if123wasstuck closed,the control rod would not withdraw,but ia tlsowouldn't initially insert orshow 4 gpmdrive water flow initially.
| |
| Technical Reference(s): SDLP-03F Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-03F 1.10.e Question Source: Bank 16-1 NRC#38 Question History: 16-1 NRC#38 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(6)
| |
| Comments:
| |
| | |
| ES-401 WrittenExamination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier
| |
| # 2 Group # 2 K/A# 201002 K1.05 Importance Rating3.4 Reactor Manual Control Knowledge ofthephysical connections and/orcause-effect relationships between REACTOR MANUALCONTROL SYSTEM andthefollowing: Rodworth minimizer: Plant-Specific Proposed Question: #56 A plant isinprogress startup withthefollowing:
| |
| a APRMsindicate 5%andstable.
| |
| * TheRodWorth Minimizer(RWM) NORMAL BYPASS keylock switchisinNORMAL.
| |
| a AnOperator iswithdrawing the first rod in a group (22-31).
| |
| control a Thegroup withdraw limit is24.
| |
| * TheOperator erroneously withdraws controlrod22-31 to position 26.
| |
| a Then,the Operator selectsthenext control rodinthe same group (30-31).
| |
| Which oneofthe following describesthe ability tomovecontrol rods 30-31 and 22-31 withthe Reactor Manual Control System (RMCS)?
| |
| Control Rod30-31 Control Rod22-31 A. Canbemoved Canbeinserted, only B. Canbemoved Canbewithdrawn andinserted C. CANNOT bemoved Canbeinserted, only D. CANNOT bemoved Canbewithdrawn andinserted
| |
| | |
| Proposed Answer: C Explanation: With Reactor power below 10%andtheRWMNORMALBYPASS switch keylock in NORMAL, theRWMis enforcing theprogrammed rodsequence. Control rod22-31hasbeen withdrawnbeyond the withdraw limit. Thisresultsinawithdraw error andwithdraw block for control rod22-31. Control rod 22-31 canbeinserted withRMCS tocorrectthe Until error. the withdraw is corrected, error all other control rods have withdraw andinsert blocks imposed.
| |
| A. Incorrect -
| |
| Control rod 30-31 withdraw andinsert areblocked. because Plausible onlyone control rodpositioning error exists,andin somecases multiple areallowed toexist before resulting ina block.
| |
| B. Incorrect -
| |
| Control rod 30-31 withdraw andinsert areblocked. Plausible becauseonlyone control rodpositioning errorexists, and insomecases multiple areallowed toexist before resulting ina block. Control rod 22-31 withdraw is blocked. Plausiblebecausethecontrol rod isonly withdrawn asingle notch past the group limit andnoother errors exist.
| |
| D. Incorrect -
| |
| Control rod 22-31 withdraw isblocked. Plausible because thecontrol rodisonly withdrawn asingle notch past thegroup limit andnoother errors exist.
| |
| Technical Reference(s): OP-64 Proposed references tobeprovided toapplicantsduring examination: None Learning Objective: SDLP-03D 1.05.b.4, 1.05.b.5 Question Source: Bank 9/12 NRC#55 Question History: 9/12 NRC#55 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(6)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier
| |
| # 2 Group # 2 K/A# 202001 K5.10 Importance Rating2.8 Recirculation Knowledge oftheoperational implications ofthefollowing concepts astheyapply to RECIRCULATION SYSTEM: Motor generator setoperation: Plant-Specific Proposed Question: #57 Theplant isoperatingat100%power when a leakcauses fluid drive oil inRWRMGsetA level tolower.
| |
| Which oneofthe following describes theresultingbehavior ofRecirculation loopA flow?
| |
| Recirculation loop A flow...
| |
| A. Rises B. Lowers C. Remains stable duetoautomatic lock ofthe scoop tube D. Remains stable duetoautomatic adjustment ofscoop tube position
| |
| | |
| Proposed Answer: B Explanation: TheRWRMGsetdrive motor iscoupled tothe generator throughafluid drive that isused tovary speed generator.
| |
| the o f the The amount of oil inthe f drive luid working circuit determines thespeed ofthe generator. Asoil isremoved from theworking the circuit, generator slows down. Theamount ofoil removed from theworking circuit isnormally controlled byscoop tube position. However, with a leak causing oillevel the tolower, scoop tube isnolongerin control. With less oil coupling the twomachines, generatorspeed lowers, which cause Recirculation loopA flow tolower.
| |
| A. Incorrect -
| |
| Recirculation loop A flow lowers, notrises. Plausible because does speed change andthis would be the answer if the operation ofthe fluid drive coupling was misunderstood.
| |
| C. Incorrect -
| |
| Recirculation loopA flow lowers. Plausible because thereisanautomaticscoop tube lockup onmultiple conditions, including low oil pressure, which couldbeanissueif conditions degraded such that oilpressure waslost.
| |
| D.Incorrect -
| |
| Recirculation loop A flow lowers. Plausible ifcandidate believed therewasa feedback circuitinthe scoop tube positioning controls that attempted tomaintain constant generator speed.
| |
| Technical Reference(s): OP-27 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-02H 1.05.a.9 Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(6)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 2 K/A# 204000 K4.06 Importance Rating2.6 Reactor WaterCleanup Knowledge ofREACTORWATER CLEANUP SYSTEM design feature(s) and/or interlocks which provide exchanger) for thefollowing: Maximize plant efficiency (use ofregenerative heat Proposed Question: #58 Theplant isoperatingat50%power withthe following:
| |
| a Preparations areunderway fora plant shutdown.
| |
| a RWCUBlowdown istobeestablished toRadwaste for post-maintenance testing.
| |
| Which oneofthe following describes the effect ofestablishing RWCU Blowdown flowonNRHX outlet temperature andplant efficiency?
| |
| M A. Rises Rises B. Rises Lowers C. Lowers Rises D. Lowers Lowers
| |
| | |
| Proposed Answer: B Explanation: Establishing RWCUBlowdown flow diverts someofthewater that would otherwise pass through theregenerative heat exchanger. This leads toless ofthe cooling incoming coolant to the RWCUsystem, which raises NRHXoutlet temperature.This also rejects heat from returning totheReactor coolant system, increasing makeup fromtherelatively cold Hotwell. The additional heating that mustbedoneonthis makeup water plant reduces efficiency.
| |
| A. Incorrect -
| |
| Plant efficiency lowers. Plausible because less cooling occursontheincoming water toRWCU,which could bethoughtofasless lossofheat oftheplant ina portion cycle.
| |
| C.Incorrect -
| |
| NRHXoutlet temperature rises. Plausible iftheBlowdown flowpath and cause/effect relationship isnotunderstood. Plant efficiency lowers. Plausible because less cooling occurs onthe incoming water toRWCU, which could bethought ofaslessloss of heat inaportion ofthe plant cycle.
| |
| D. Incorrect -
| |
| NRHXoutlet temperature rises. Plausible iftheBlowdown flowpath and cause/effect relationship isnotunderstood.
| |
| Technical Reference(s): OP-28 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-12 1.13.c Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(3)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 2 K/A# 214000K6.02 Importance Rating2.7 RodPosition Information Knowledge oftheeffectthat a lossormalfunctionofthefollowing haveontheROD will POSITION INFORMATIONSYSTEM: Positionindication probe Proposed Question: #59 Theplant isoperating at80%power with the following:
| |
| a A controlrodisnotch withdrawn from position 46toposition 48.
| |
| a Misalignment oftheposition indicating probe reed switchescauses thefollowing when the controlrod settles:
| |
| o Theposition 47reed switch isclosed.
| |
| o Theposition 48reed switch isopen.
| |
| Which oneofthe following describes the effect ofthis malfunction?
| |
| Annunciator.,
| |
| A. 09-5-2-3, RodDrift, alarms whenthe control rodtime timesout.
| |
| B. 09-5-2-3, RodDrift, alarms whenthenext control rodisselected.
| |
| C. 09-5-2-4, RodOvertravel, alarms whenthecontrol rod timetimes out.
| |
| D. 09-5-2-4, RodOvertravel, alarms whenthenext control rodisselected.
| |
| | |
| Proposed Answer: A Explanation: Annunciator 09-5-2-3, RodDrift, alarms whenthecontrol rodtimetimes out because the control rod fails toindicate ataneven (position position 48reed isopen) switch anddoesindicate atanoddposition (position 47reed switch isclosed).
| |
| B. Incorrect -
| |
| The annunciator alarms assoon asthetimer times out,notlater whenthenext rodisselected. Plausible that the alarm would beblocked while a rodisselected andhas been movedsince odd reedswitch positions areexpected tobepicked upduring this evolution.
| |
| C.incorrect -
| |
| Annunciator 09-5-2-4, RodOvertravel, does not alarm. Plausible because this would becorrect for a different combination ofreed switch malfunctions(48 49 open, closed).
| |
| D.Incorrect -
| |
| Annunciator 09-5-2-4, Rod Overtravel, does notalarm. Plausible because this would becorrect for a different combination ofreedswitch malfunctions(48 49 open, closed). Thecorrect annunciator alarms assoon asthe timer timesout,notlater whenthe next rod isselected. Plausible that the alarm would beblocked while a rodisselected and hasbeen moved since oddreed switch positions areexpected tobepickedupduring this evolution.
| |
| Technical Reference(s): ARPs09-5-2-3and 09-5-2-4 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-03G 1.05.a.3 Question Source: BankSSESLOC28NRC#32(2016)
| |
| Question History: SSESLOC28NRC#32(2016)
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(6)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 2 K/A# 215001 A2.07 Importance Rating3.4 Traversing inCoreProbe Ability to(a) predict theimpacts ofthefollowing ontheTRAVERSING IN-COREPROBE; and(b) based onthose predictions, useprocedures tocorrect, control, the ormitigate consequences ofthose abnormal conditions oroperations: Failure toretractduring accident conditions: Mark-l&ll Proposed Question: #60 Theplant isoperatingat100%power with the following:
| |
| = Traversing In-Core Probe (TIP) scans arein progress with TIPSystem 1detector inthe core.
| |
| * A coolant leak develops intheDrywell.
| |
| = Drywell pressure is3 psig andrising.
| |
| a TIPSystem 1detector fails toretract automatically and manually.
| |
| Which oneofthe following describes theresulting operation oftheTIP System 1shear valve?
| |
| TheTIPSystem 1shear valve..
| |
| A. automatically closes immediately.
| |
| B. automatically closes after a time delay.
| |
| C. mustbemanually closed using a switch atthe TIPRoom.
| |
| D. mustbemanually closed using a switch onControl Roompanel 09-13.
| |
| | |
| Proposed Answer: D Explanation: TheTIPshear valves areprovided asa backup tothe primary normal containment isolation feature. Thenormal primarycontainment feature isolation automatically retracts the detector andthen closes the associated ball valve. Ifthedetector fails the toretract, ball valve cannot close, thus the shear isprovided valve tocutthrough thedetector cable and isolate the containment penetration. Noautomatic shear valve actuation isprovided.
| |
| The operator must detect the failure and manually actuate theshear valve.
| |
| Thecontrol for switch this action isonControl Room Panel 09-13.
| |
| A. Incorrect -
| |
| Theshearvalve does NOTautomatically close. Plausible that itwouldclose after atime delay onfailure to retract, asthis isthe design purposes ofthevalve.
| |
| B. incorrect -
| |
| Theshear valvedoes NOT automatically close. Plausible it that wouldclose after atime delay onfailure toretract, asthis isthe design purposes ofthevalve.
| |
| C.Incorrect -
| |
| Theshear valve isfired from Control RoomPanel Plausible 09-13. because this isaninfrequently used control andsome manual actions canbedone fromTIProoms.
| |
| Technical Reference(s): AOP-15, SDLP-07F Proposed references tobeprovided toapplicantsduring examination: None Learning Objective: SDLP-07F 1.05.b.1, 1.05.b.2 Question Source: Bank 9/12 NRC#57 Question History: 9/12 NRC#57 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 2 K/A# 215002 A4.03 Importance Rating2.8 RodBlock Monitor Ability tomanually operate and/or monitorinthe control room: Trip bypasses Proposed Question: #61 Theplant isoperating at20%power with the following:
| |
| = A hardware problem hasoccurredon Rod BlockMonitor(RBM) A.
| |
| a Thehardware malfunction isequivalent to the RBMA modeswitch being of out OPERATE.
| |
| Which oneofthe following describes the status ofRBMA and control rodblocks?
| |
| RBMA is...
| |
| A. auto-bypassed. NOcontrol rodblocks areenforced.
| |
| B. NOTauto-bypassed. NOcontrol rodblocks areenforced.
| |
| C. NOTauto-bypassed. A control rod withdraw isenforced, block only.
| |
| D. NOTauto-bypassed. Control rod withdraw andinsert blocks areenforced.
| |
| | |
| Proposed Answer: A Explanation: TheRBMisauto-bypassed since power isbelow norodblocks 30%.Therefore, arereceived.
| |
| B. Incorrect The RBMisauto-bypassed since power 30%.Plausible isbelow becausethis would becorrect ifpower was>30%andthe hardware wasnotcausing failure theINOPtrip.
| |
| C. Incorrect -
| |
| RBM A is auto-bypassed. Plausible because this would if becorrect powerwere
| |
| >30%.
| |
| D.Incorrect -
| |
| RBMA is auto-bypassed. Plausible because this wouldbecorrecta RWM for INOPtrip duringa startup.
| |
| Technical Reference(s): OP-16, ARP09-5-2-45 Proposed references tobeprovidedto applicants duringexamination:None Learning Objective: SDLP-07C1.05.c.4.e Question Source: Modified Bank 17-1 NRC #35 Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| RBM Ability tomonitor automatic operations oftheRODBLOCK MONITOR SYSTEMincluding Alarm andindicatinglights: BWR34 5 Proposed Question: #35 Theplantis operating at50%power with the following:
| |
| A hardware problem hasoccurred onRodBlock Monitor (RBM) A.
| |
| * Annunciator 09-5-2-45, RBMUPSCALE ORINOP, alarms.
| |
| TheINOP white light isilluminated for RBMA onPanel 09-14.
| |
| Which oneofthe following ($scribesthe status ofRBMA andcontrol rodblocks?
| |
| RBMA is..
| |
| A,-autebypagagL NOcontrol rod blocks are enforced.
| |
| B. NOTauto-bypassed. NOcontrol rod blocks are enforced.
| |
| C NOTauto-bypassed. A control rod withdrawblock is enforced, only.
| |
| D. NOTauto-bypassed. Control rod withdraw andinsert blocks areenforced.
| |
| JAF1-1NRC
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier
| |
| # 2 Group # 2 K/A# 219000 A4.04 Importance Rating3.0 RHR/LPCI: Torus/Suppression PoolCooling Mode Ability tomanually operate and/or monitorinthe control room: Minimum flow valves Proposed Question: #62 Theplant isoperating at100%powerwith thefollowing:
| |
| a RHRA isbeing placedinTorus Cooling in preparation for HPCItesting.
| |
| a AnOperator isabout tostartRHRpump A.
| |
| Which oneofthe following describestheoperation of10MOV-16A, MINFLOWVLV,during this evolution?
| |
| 10MOV-16A isinitially.
| |
| A. openandcloses whenRHRloop A flow reaches approximately 1500 gpm.
| |
| B. openandcloses whenRHRloop A flow reaches approximately 6500 gpm.
| |
| C. closed, opens whenRHRpumpA starts, andcloses whenRHRloop A flow reaches approximately 1500gpm.
| |
| D. closed, opens whenRHRpumpA starts, andcloses whenRHRloop A flow reaches approximately 6500gpm.
| |
| | |
| Proposed Answer: A Explanation: Thenormal standby lineup has10MOV-16A fully openprior ofRHRpump tostart A.10MOV-16A automatically closes whenRHRloop A flow reaches approximately 1500gpm.
| |
| B.Incorrect10MOV-16A automatically closes whenRHRloop A flow reaches approximately 1500 gpm.Plausible because 6500 gpmis theminimum required tobeestablished flow with oneRHRpump running.
| |
| C.Incorrect -
| |
| 10MOV-16A isinitially open.Plausible thatthenormal standby would lineup have thevalve closed and it would only open whena pumpwasrunning with lowflow.
| |
| D.Incorrect -
| |
| 10MOV-16Ais initially open. Plausible thatthe normal standby would lineup have the valve closed andit would only open whena pumpwasrunning lowflow.
| |
| with 10MOV-16A automatically closes when RHRloop A flow reaches approximately 1500gpm.
| |
| Plausible because 6500gpmisthe minimum required flow oneRHR with tobeestablished pumprunning.
| |
| Technical Reference(s):OP-13, OP-13B Proposed references tobeprovided toapplicantsduring examination: None Learning Objective: SDLP-10 1.05.a.1.b Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(8)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 2 Group # 2 K/A# 223001 A3.04 Importance Rating4.2 Primary Containmentand Auxiliaries Ability tomonitor automatic operations ofthePRIMARY CONTAINMENT SYSTEM AND AUXILIARIES including: Containment /drywell response during LOCA Proposed Question: #63 Which oneofthe following describes effect thatafailed the open Torus toDrywell vacuum breaker wouldhave onPrimary Containment response toa design-basisloss ofcoolant accident?
| |
| A. Bothpeak Torus andDrywell pressureswould be lower than expected.
| |
| B. Bothpeak Torus andDrywell pressureswould begreater than expected.
| |
| C. PeakTorus pressure would behigher thanexpected andpeak Drywell pressure would belower than expected.
| |
| D. PeakTorus pressure would belower thanexpected andpeakDrywell pressure would be higher than expected.
| |
| | |
| Proposed Answer: B Explanation: With a failed openTorus toDrywell vacuumbreaker, theTorusandDrywell airspaces are directly connected andthe pressure-suppression featureofthePrimary Containment isbypassed. Inthe event ofa LOCA,this meanssteam notbeforced will under thewater inthe Torus andcondensed.Therefore, pressure behigher will inboththe Torusand Drywell than expected for adesign-basis LOCA.
| |
| A. Incorrect -
| |
| This malfunction does effectively expand oftheDrywell thesize airspace, which would lead tolowerpressures for very small LOCAs. However foradesign-basis LOCA,the loss ofpressure-suppression function would lead tohigher peakpressures.
| |
| C. Incorrect -
| |
| PeakDrywellpressure would also behigher during LOCA.
| |
| a design-basis D.Incorrect -
| |
| PeakTorus pressure would also behigher adesign-basis during LOCA.
| |
| Technical Reference(s):Technical Specification Bases3.6.1.7 Action B.1 Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: SDLP-16A 1.09.e Question Source: Bank 16-1 NRC#32 Question History: 16-1 NRC#32 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(9)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 2 Group # 2 K/A# 256000 K3.02 Importance Rating3.2 Reactor Condensate System Knowledge oftheeffectthat a lossormalfunctionoftheREACTOR CONDENSATE SYSTEM willhaveonfollowing: CRD hydraulics system Proposed Question: #64 Theplant isoperatingat100%power when allCondensate pumps trip.
| |
| Which oneofthe following describes theimpactof the loss ofall Condensate pumps onCRD?
| |
| CRD...
| |
| A. loses a backup source ofwaterbut retainsthenormalsource.
| |
| B. loses the normal source ofwater butautomatically swapsto the backup source.
| |
| C. loses the normal source ofwater andmustbemanually swapped to take suctionfrom the Torus.
| |
| D. loses thenormal source ofwaterandmustbemanually swapped totake suction from the Condensate Storage Tanks.
| |
| | |
| Proposed Answer: B Explanation: CRDnormally takes suction from theCondensate pumpdischarge header througha pressure control valve. Whenall Condensate pumps trip, inthis pressure header is lost. CRDsuction automatically swaps tothebackup source (Condensate Storage Tanks) through a check valve.
| |
| A. Incorrect -
| |
| The discharge of the Condensate pumps isthenormal sourceofwatertothe CRDpumps. Plausible that the Condensate S torage Tanks would bethe normalsource with thedischarge of the Condensate pumpsasabackup.
| |
| C.Incorrect -
| |
| CRDsuction automatically swaps tothebackup source through a checkvalve.
| |
| Plausible that the Toruscould bemanually aligned asa backup, asit isa largevolume of water used foremergencies.
| |
| D.Incorrect -
| |
| CRDsuction automatically swapstothe backup source acheck through valve.
| |
| Plausible transfer that totheCondensate Storage Tanks would bemanual,notautomatic.
| |
| Technical Reference(s): OP-25 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-03C 1.10.a Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(6)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier
| |
| # 2 Group# 2 K/A# 241000K1.31 ImportanceRating3.1 Reactor/Turbine Pressure Regulating Knowledge ofthephysical connections and/orcause-effect relationships between REACTOR/TURBINE PRESSURE REGULATING SYSTEM andthefollowing:Turbine protection Proposed Question: #65 A plant isinprogress startup with the following:
| |
| * TheMain Turbine isbeing started.
| |
| * MainTurbine speed iscurrently 800rpm.
| |
| Which oneofthe following conditions will result inanautomatic Main trip?
| |
| Turbine A. ExhaustHoodtemperature of2300F.
| |
| B. EHCpumpdischarge pressure of680psig.
| |
| C. MoistureSeparator drain tank water of34".
| |
| level D. MainShaft Oil Pump(MSOP) discharge pressure of75psig.
| |
| | |
| Proposed Answer: B Explanation: LowEHCoil pressure (<1100 psig),assensed atthe oftheEHC discharge pumps,will cause anautomatic Main Turbine trip.
| |
| A. Incorrect High MainTurbine Exhaust Hoodtemperature (>225oF)originally caused aMain Turbine trip,but this trip hasbeenremoved byplant A manual modification. MainTurbine trip isstill required ifthistemperature isexceeded.
| |
| C.Incorrect -
| |
| High Moisture Separator drain tank water leveldoes causeanautomatic Main Turbine trip, but only if itexceeds 43". 34" ishigh,but below the trip setpoint.
| |
| D.Incorrect -
| |
| LowMSOPdischarge pressure(<105 psig) does normally provide anautomatic Main Turbine trip,however this trip isbypassedwhenMain Turbine is<1300 speed rpm.
| |
| This is toallow MSOP discharge pressure tobuild asthe Main Turbine gains speed.
| |
| Technical Reference(s):OP-9 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-94A 1.05.c.1 Question Source: Bank 16-1 NRC#30 Question History: 16-1 NRC#30 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 3 Group #
| |
| K/A# 2.1.26 Importance Rating3.4 Knowledge ofindustrial safety procedures (such asrotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen andhydrogen).
| |
| Proposed Question: #66 A tagout isbeing developed forawater system withthefollowing conditions:
| |
| a Highestsystem water temperature: 3000F
| |
| * Highestsystem water pressure: 100 psig Which oneofthe following describes theneed toprovide dual valveisolation, inaccordance with OP-AA-109-101, Clearance andTagging?
| |
| Inaccordance with OP-AA-109-101, dual valve isolation should...
| |
| A. NOTbeprovided.
| |
| B. beprovided, duetopressure only.
| |
| C. beprovided, duetotemperature only.
| |
| D. beprovided, duetoboth pressure andtemperature.
| |
| | |
| Proposed Answer: C Explanation: OP-AA-109-101 states that dual valveisolation shouldbeprovided when isolating from anenergysource having atemperature than greater 2000Forpressure greater than 500psig. Therefore, this system should have dual valveisolation basedonatemperature of>2000F, but not based onpressure.
| |
| A. incorrect -
| |
| This should have dual valve isolation based of>2000F.
| |
| onatemperature B. Incorrect -
| |
| This should havedual valve but isolation, basedontemperature, notpressure.
| |
| Thehighest systemwater pressure is below of500psig.
| |
| thethreshold D. Incorrect -
| |
| This should have dualvalve butbased isolation, ontemperature, notpressure.
| |
| Thehighest system water pressure isbelow thethreshold of500psig.
| |
| Technical Reference(s): OP-AA-109-101 Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: LP-AP 44.09.d Question Source: Bank 14-2 NRC#67 Question History: 14-2 NRC#67 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 3 Group #
| |
| K/A# 2.1.44 Importance Rating3.9 Knowledge ofROduties inthecontrol roomduring fuel handling suchasresponding to alarms fromthefuel handling area, communication with thefuei storage facility,systems operated fromthecontrol room insupportoffueling operations, andsupporting instrumentation.
| |
| Proposed Question: #67 A refueling outage isinprogress withthe following:
| |
| a Thecore isfullyloaded withfuel.
| |
| a Thefollowing evolutions areplanned onthe next shift:
| |
| (1) TheRefuel Bridge willbere-arranging irradiated fuel bundles intheSpent FuelPool.
| |
| (2) TheRefuel Bridge bereplacing will control rods in the Reactor core.
| |
| Which oneofthe following describes therequirement for maintaining continuous communications between a licensed operator inthe Control Roomand the Refuel Bridge during these evolutions, inaccordance withOSP-66.001, Management ofRefueling Activities?
| |
| Continuous communications between a licensed operator intheControl Roomand the Refuel Bridge is..
| |
| A. required during both ofthese evolutions.
| |
| B. NOTrequired during eitherofthese evolutions.
| |
| C. required during evolution butNOTduring (1), evolution (2).
| |
| D. requiredduring evolution butNOTduring (2), evolution (1).
| |
| | |
| Proposed Answer: D Explanation: OSP-66.001 requires continuous communication betweena licensed in operator theControl Room andtheRefuel Bridge during theperformance ofcore Replacing alterations.
| |
| control rod blades in the core during evolution (2)isa core alteration. Movingirradiated fuel bundles during evolution (1) isnotacore alteration anddoes notrequirecontinuous communicationwith theControl Room.
| |
| A. Incorrect -
| |
| Continuous communication between a licensed operatorinthe Room Control andthe Refuel Bridge is notrequired during evolution (1). Plausiblebecausethis evolution does involve movement of irradiated fuel.
| |
| B.Incorrect -
| |
| Continuous communication between alicensed operatorinthe Room Control andthe Refuel Bridge isrequired during evolution (2).Plausible because thisevolution does notinvolve fuel andcontrol rod blade replacements arealways done indefueled cells.
| |
| C.Incorrect -
| |
| Continuous communication between a licensed operatorinthe Room Control andthe Refuel Bridge isnotrequired during evolution (1). Plausiblebecausethis evolution does involve movement ofirradiated fuel.
| |
| Technical Reference(s): OSP-66.001 Proposed references tobeprovided toapplicants during examination: None Learning Objective:
| |
| Question Source: BankNMP12015Cert
| |
| #67 Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content: 55.41(13)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 3 Group #
| |
| K/A# 2.1.37 Importance Rating4.3 Knowledge ofprocedures, guidelines, orlimitations associated with reactivity management.
| |
| Proposed Question: #68 Given the followingindividuals:
| |
| (1) A qualified, non-licensed Equipment Operator whohasbeen selected forlicense class but hasnotyetbegun formal license class training.
| |
| (2) Aninstant SROcandidate whoisperforming thepre-license class familiarization plant guide.
| |
| (3) AnROlicense candidate whoiscompleting thein-plant OJTphase oflicense class.
| |
| Which oneofthe following identifies theindividual(s) that maybe allowed toperform reactivity manipulations intheplant under theguidance ofa licensed Reactor Operator, inaccordance with OP-AA-300, Reactivity Management, andOP-AA-103-103, Operation ofPlantEquipment?
| |
| A. (3)only B. (1)and(3) only C. (2)and(3) only D. (1), and(3)
| |
| (2),
| |
| | |
| Proposed Answer: A Explanation: OP-AA-300 and OP-AA-103-103 allows anROtodirect a non-licensed individual toperform reactivity manipulations under their guidance incertain circumstances:
| |
| * Thenon-licensed individual shall beanactive participant inanongoing Licensed Operator Training class.
| |
| = Theindividual shall have mettheknowledge requirements asdefined intheLicensed Operator Training program.
| |
| Theknowledge requirements intheLicensed Operator Training program include completion of related Generic Fundamentals and reactivity control system training. Since (3) individual is the only onehaving completed those requirements toget tothe in-plant phase oflicenseclass, they aretheonly individual allowed toperform reactivity manipulations under instruction.
| |
| B. Incorrect -
| |
| Individual (1) isnotyet allowed toperformreactivity manipulations. Plausible because they are qualified toperformnon-licensed activities andwill eventuallybeallowed toperform under instruction reactivity manipulations prior tobeing licensed.
| |
| C.incorrect -
| |
| Individual (2) isnotyet allowed to perform reactivitymanipulations. Plausible because they areina preparatory phase ofthe licensed operatortraining programandwill eventually beallowed toperform under instruction reactivity manipulations tobeing prior licensed.
| |
| D. Incorrect -
| |
| Individual (1) isnotyetallowed toperformreactivity manipulations. Plausible because they are qualified toperform non-licensed activities and will eventuallybeallowed toperform under instruction reactivity manipulations prior to being licensed. (2)
| |
| Individualis not yet allowed toperform reactivity manipulations. Plausiblebecause they areina preparatory phase ofthelicensed operator training program andwill eventually beallowed toperform under instruction reactivity manipulations prior tobeing licensed.
| |
| Technical Reference(s): OP-AA-300, OP-AA-103-103 Proposed references tobeprovided toapplicants during examination: None Learning Objective:
| |
| Question Source: Bank PB2017NRC#66 Question History: PB2017NRC#66 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 3 Group #
| |
| K/A# 2.2.14 Importance Rating3.9 Knowledge oftheprocess for controlling equipment orstatus.
| |
| configuration Proposed Question:#69 Which oneofthefollowing combinations oftags isNOTallowedtobesimultaneously applied to a single component, inaccordancewith OP-AA-109-101, Clearance andTagging?
| |
| A. TwoDanger Tags B. A Danger Tagandaninformation Tag C. A SpecialCondition Taganda Danger Tag D. A SpecialCondition TagandanInformation Tag
| |
| | |
| Proposed Answer: C Explanation: OP-AA-109-101 prohibits simultaneous placement ofa Danger Taganda Special Condition Tagonasingle component.
| |
| A. Incorrect Two-Danger Tagsmaybesimultaneous applied onasingle component.
| |
| Plausible because theprocedure does contain a restriction for thispairing (positions cannot conflict).
| |
| B. Incorrect -
| |
| A Danger Tag andanInformation Tagmaybesimultaneous ona single applied component. Plausible because the procedure does contain for a restriction pairing this (positions cannot conflict).
| |
| D.Incorrect -
| |
| A Special Condition TagandanInformation Tagmaybesimultaneous applied onasingle component. Plausible because the procedure does restrictions contain forthis pairing (positions cannot conflict and Information Tag cannot obstruct Condition Special Tag).
| |
| Technical Reference(s): OP-AA-109-101 Proposed references tobeprovided toapplicants during examination: None Learning Objective: LP-AP 44.05 Question Source: BankNMP22017 Cert #69 Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 3 Group #
| |
| K/A# 2.2.39 Importance Rating3.9 Knowledge oflessthan orequaltoonehour Technical Specification action statements for systems.
| |
| Proposed Question: #70 Theplant isoperatingat100%power.
| |
| Which oneofthe followingconditions requires action inonehour inaccordance orless, with Technical Specifications?
| |
| A. MAPRAT at1.1 B. Drywellpressure at1.4 psig C. Torus water temperature at1110F D. RCSunidentified leakage at10gpm
| |
| | |
| Proposed Answer: C Explanation: With Torus water temperature at1110F, Technical Specification requires 3.6.2.1 immediate action toscram theReactor.
| |
| A. Incorrect -
| |
| With MAPRAT at1.1, theAPLHGR thermal limitisSAT.Plausible because Technical Specification 3.2.1 doeshavea2hour requirement basedonMAPRAT.
| |
| B. Incorrect -
| |
| With Drywell pressure at1.4 psig, Technical Specification isSAT.
| |
| 3.6.1.4 Plausible because this Technical Specification does require action within 1houriD frywell pressure exceeds 1.95 psig.
| |
| D. Incorrect -
| |
| With RCSunidentified leakage at10gpm,Technical Specification isnot 3.4.4 met, but only requires action within 4 hours. Plausible because Technical Specification 3.4.4 isnot metanddoes require action within afairly short amountoftime.
| |
| Technical Reference(s):Technical Specifications 3.2.1, 3.6.2.1 3.6.1.4, 3.4.4, Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: SDLP-16A 1.16 Question Source: BankSSESLOC28RNRC #54(2017)
| |
| Question History: SSESLOC28R NRC#54(2017)
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 3 Group #
| |
| K/A# 2.2.22 Importance Rating4.0 Knowledge oflimiting conditions for operations andsafety limits.
| |
| Proposed Question: #71 Theplant experienced a failureto scram with the following:
| |
| = Thepeak Reactor pressure during thetransient was1350 psig.
| |
| Thelowest Reactor water level during the transient was20".
| |
| Which oneofthe following describes whether the Reactor pressure and Reactor level water Safety Limitswereexceeded orNOT,inaccordance with Technical Specifications?
| |
| M A. Exceeded Exceeded B. Exceeded NOT exceeded C. NOTexceeded Exceeded D. NOTexceeded NOTexceeded
| |
| | |
| Proposed Answer: B Explanation: TheReactor pressure Safety Limit (1325 psig)wasexceeded.
| |
| TheReactor water level Safety (>
| |
| Limittopofactive fuel, or0") wasnotexceeded.
| |
| A. Incorrect -
| |
| The Reactor water exceeded.Plausible because level levelSafety ismuchlower
| |
| (>
| |
| Limittopofactive than or0")
| |
| fuel, andnear normal wasnot ofactive top fuel.
| |
| C. Incorrect -
| |
| The Reactor pressure Safety Limit (1325 psig) Plausible wasexceeded.
| |
| because peak pressure isjust slightlyabove thelimit. TheReactor water Safety level Limit
| |
| (> andneartopof active fuel.
| |
| t normal op ofactive fuel, or 0") was not exceeded. Plausible because is levelmuchlower than D. Incorrect -
| |
| TheReactorpressure SafetyLimit (1325 psig)wasexceeded.
| |
| Plausible because peak p ressure is slightly above j ust thelimit.
| |
| Technical Reference(s):Technical Specification 2.0 Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: SDLP-02D 1.16 Question Source: Bank2010NRC#12 Question History: 2010NRC#12 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content: 55.41(10)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 3 Group #
| |
| K/A# 2.3.5 Importance Rating2.9 Ability touseradiation monitoring systems, suchasfixed radiation monitors andalarms, portable survey instruments, personnel monitoring equipment, etc.
| |
| Proposed Question: #72 Theplant isoperating at100%power with the following:
| |
| = Movement ofradioactive material in the Reactor Buildingcauses Area Radiation Monitor (ARM) #25, RXBLDGEL272EAST HCU AREA, togointo alarm high.
| |
| * Annunciator 09-3-1-40, RXBLDGARM RAD HI, isreceived andacknowledged.
| |
| Which oneofthe following describeshowAnnunciator 09-3-1-40 will respondtothe following twoindependent conditions?
| |
| Ifa second ARMinput exceeds its high alarmsetpoint,thenAnnunciator 09-3-1-40 (1) -.
| |
| lfARM#25returns tonormal, then Annunciator 09-3-1-40 (2) .
| |
| A. re-flashes canbereset beforedepressing ARM RESETpushbutton(s)
| |
| B. re-flashes CANNOT beresetbefore depressing ARMRESET pushbutton(s)
| |
| C. doesNOTre-flash canbereset beforedepressing ARM RESETpushbutton(s)
| |
| D. doesNOTre-flash CANNOT beresetbefore depressing ARMRESET pushbutton(s)
| |
| | |
| Proposed Answer: D Explanation: Annunciator 09-3-1-40 will actuate uponreceipt ofa high alarm from condition anyof16 Area Radiation Monitors (ARMs). However, once theannunciatorisin, it will notre-flash for any subsequent high alarm conditions from anyofthe other ARMs.Additionally, once thehigh radiation condition clears, thehigh alarm tripissealed inuntil theRESETpushbutton is depressed onthe corresponding ARMtrip unit oncontrol roompanel 09-11.Until thisRESET pushbutton isdepressed, both the ARMtrip unit amber HIGHlight 09-3-1-40 andAnnunciator willbesealed in.
| |
| A. Incorrect -
| |
| Theannunciator does nothave re-flash capability. Plausible becauseother annunciators dohave re-flash capability andit would behelpful additional toidentify areas developing high radiation. The annunciator cannot bereset until ARMRESET the pushbutton isdepressed. Plausible because other annunciators without clear theneedfor manual action atthe tripping device.
| |
| B.Incorrect -
| |
| Theannunciator does not have re-flash capability. Plausible becauseother annunciators dohave re-flash capability and it wouldbehelpful toidentify additional areas developing high radiation.
| |
| C. Incorrect -
| |
| Theannunciator cannot bereset until theARMRESET isdepressed.
| |
| pushbutton Plausible because other annunciators clear without theneed formanualaction atthe tripping device.
| |
| Technical Reference(s): ARP09-3-1-40, 1.78-98, UFSAR Fig7.13-1 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-17 1.14.d.5 Question Source: Bank9/12 NRC#73 Question History: 9/12 NRC#73 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content: 55.41(11)
| |
| Comments:
| |
| | |
| ES-401 Written Question Examination Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier# 3 Group #
| |
| K/A# 2.4.41 ImportanceRating2.9 Knowledge oftheemergency actionlevel andclassifications.
| |
| thresholds Proposed Question: #73 Which oneofthe following describes thelowestEmergency Action (EAL)
| |
| Level atwhich the full Emergency Response Organization (ERO) is tobestaffed?
| |
| required A. Unusual Event B. Alert C. SiteAreaEmergency D. GeneralEmergency
| |
| | |
| Proposed Answer: B Explanation: TheAlert EALis thelowest level atwhichthe EROisrequired full tobestaffed.
| |
| A. Incorrect -
| |
| The Alert EALis the lowest level atwhich the EROisrequired full tobestaffed.
| |
| Plausiblebecause precautionary staffing oftheEROisallowed attheUnusual Event level.
| |
| C. incorrectThe Alert EAListhelowest level atwhich EROisrequired full the tobestaffed.
| |
| Plausible because the full EROisstaffed atthe SiteAreaEmergencylevel also.
| |
| D. incorrect -
| |
| TheAlert EAL is the lowest level atwhich the EROisrequired full tobestaffed.
| |
| Plausible because the full EROis staffed atthe General level Emergency also.
| |
| Technical Reference(s): EP-AA-112-100-F-50 Proposed references tobeprovided to applicants during examination:None Learning Objective:
| |
| Question Source: BankNMP12010 NRC #72 Question History: NMP12010 NRC#72 Question Cognitive Level:Memory orFundamentalKnowledge 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 3 Group #
| |
| K/A# 2.4.3 Importance Rating3.7 Ability toidentify post-accident instrumentation.
| |
| Proposed Question: #74 Which oneofthe following instruments isNOTrequired Post Monitoring Accident (PAM) instrumentation, inaccordance with Technical Specifications?
| |
| A. Toruswater level B. Toruswater temperature C. Average power range monitor D. Containment high range radiation monitor
| |
| | |
| Proposed Answer: C Explanation: Ofthegiven instruments, only average power range (APRMs) monitors arenot requiredby TS 3.3.3.1, PAMInstrumentation.
| |
| A. Incorrect Torus waterlevel instrumentation isrequired byTS3.3.3.1 Plausible because this instrument does not directly monitor theReactor.
| |
| B.Incorrect -
| |
| Torus water temperature instrumentation isrequired byTS3.3.3.1 Plausible because this instrument does not d irectlymonitor theR eactor.
| |
| D.Incorrect -
| |
| Containment high range radiation instrumentation byTS3.3.3.1 isrequired Plausible because thisinstrument isnot widely used byoperators.
| |
| Technical Reference(s): Technical Specification 3.3.3.1 Proposed references tobeprovided to applicants during examination: None Learning Objective:
| |
| Question Source: Bank NMP12009 Cert #72 Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.41(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level RO Tier # 3 Group #
| |
| K/A# 2.4.26 Importance Rating3.1 Knowledge offacility protection requirements, including firebrigade andportable fire fighting equipment usage.
| |
| Proposed Question: #75 Theplant isoperating at100%power with the following:
| |
| = Maintenance personnel a fire has developed inthe report East Electric Bay.
| |
| * A hightemperature alarm has been received for this zone ontheFire Protection Panel.
| |
| * NOother adverse effects fromthe firehave been observed.
| |
| Which oneofthe following describes the operationalresponse required for these conditions in accordance withFPP-1.2, Fire Fighting, andAOP-28, Operation DuringPlant Fires?
| |
| A. Dispatch the full Fire Brigade. Inserting a manualReactor scram isrequirednow.
| |
| B. Dispatch the full Fire Brigade. Inserting a manualReactor scram isNOTyet required.
| |
| C. Dispatch theFire Brigade Leader toassess theneed forfullFireBrigade activation.
| |
| Insertinga manual Reactor scram isrequired now.
| |
| D. Dispatch theFire Brigade Leader toassess theneed forfullFireBrigade activation.
| |
| Insertinga manual Reactor scram isNOTyet required.
| |
| | |
| Proposed Answer: B Explanation: FPP-1.2contains guidance forControl RoomOperator responsetoa report from personnel ofa fire inthe plant.This guidance requires dispatching the full FireBrigade,NOT just theFire Brigade Leader.AOP-28 containscriteria for whena Reactor scamisrequired based onafire. Allfour ofthefollowing need tobemetfor a Reactor scramtoberequired based onthis fire:
| |
| a Serious firein progress (E-Plan Alertorworse) a Reactor inmode 1, 2,or3 lonization alarm atFPP, actuation offire suppression system, and/orverbal offire report a Unexplained EPICorannunciator alarm, unexplained lossofequipment, and/or unexplained actuation of equipment Thegiven required.
| |
| conditions only satisfy the2ndand 3rdwiets, thfe a Ram wam isW W A. Incorrect -
| |
| Since nounexplained alarms,equipment loss, orequipment actuationhave occurred, a Reactor scram isNOTrequiredper AOP-28 yet. Plausible becausethiswould becorrect if additional degradation of conditions weregiven.
| |
| plant C.Incorrect -
| |
| FPP-1.2 requires full Fire Brigade activation duetothe verbal ofafire.
| |
| report Plausible that theFire Brigade Leader would first be used toconfirmthe anddecide fire where tostage the fullFire Brigade. Since nounexplained alarms, equipmentlosses, or equipment actuations have occurred, a Reactor scram isNOT required per AOP-28 yet.
| |
| D. Incorrect -
| |
| FPP-1.2 requires full Fire Brigade activation ofa fire.
| |
| dueto the verbal report Plausible that theFire Brigade Leader would first beused toconfirm the fire anddecide where tostage the fullFire Brigade.
| |
| Technical Reference(s): FPP-1.2, AOP-28 Proposed references tobeprovided toapplicants during examination: None Learning Objective: LP-AOP 1.03.a Question Source: Bank 14-1 NRC#39 Question History: 14-1 NRC#39 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.41(10)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 1 Group # 1 K/A# 295021 2.1.23 importance Rating4.4 LossofShutdown Cooling Abiiity toperform specific system andintegrated plant procedures during allmodesof plant operation.
| |
| Proposed Question: #76 Theplant isshutdown for a refuelingoutage with the following:
| |
| a RHRloop B is inaShutdown CoolingLineup.
| |
| * NoRWRpumps are running.
| |
| * Irradiatedfuel movement isinprogress.
| |
| * Maintenance isinprogress which hasthe potential fordraining the Reactor vessel.
| |
| a Then, aninadvertent isolationofShutdown Cooling occurs.
| |
| * Theisolation CANNOT beimmediately restored.
| |
| * Reactorcavity water temperature is800F.
| |
| Which oneofthe following describes theneed for a Refuel Floor evacuation andrequired control ofthe maintenance which hasthe potential for draining theReactor vessel, in accordance withAOP-30, Loss ofShutdown Cooling?
| |
| Maintenance Which Hasthe Potential Refuel Floor Evacuation M A. NOTrequired Maycontinue B. NOTrequired Must besecured C. Required Maycontinue D. Required Must besecured
| |
| | |
| Proposed Answer: B Explanation: AOP-30 attachment 2 describes therequiredReactor waterlevelcontrol strategy. It requires securing andrestoring from anymaintenance which hasthepotential for draining the Reactor vessel. There isnorequirement withinAOP-30 toperforma Refuel Floor evacuation.
| |
| A. Incorrect -
| |
| AOP-30 requires securing andrestoringfrom anymaintenance whichhasthe potential for draining the Reactor vessel. Plausible because thereisnoevidencethat Reactor water levelcontrol is anissue.
| |
| C. Incorrect -
| |
| There isnorequirement within AOP-30 toperform a RefuelFloorevacuation.
| |
| Plausible because loss of SDC is a degradation ofshutdown safety, will inrising result temperatures oftheReactor coolant andtheRefuel Floor environment isindirect communication with theReactor coolant. AOP-30 requires securing andrestoring fromany maintenance which hasthepotential fordraining the Reactor vessel.Plausible because there isnoevidence that Reactor isanissue.
| |
| water level control D. Incorrect -
| |
| There isnorequirement within AOP-30 toperform a RefuelFloorevacuation.
| |
| Plausible because loss ofSDCisadegradation ofshutdown safety, will inrising result temperatures oftheReactor coolantandthe Refuel Floor environmentis indirect communication with theReactor coolant.
| |
| Technical Reference(s):AOP-30 Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: LP-AOP 1.03 Question Source: ModifiedBank 14-1 NRC#83 Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(5)
| |
| Comments:
| |
| | |
| inadvertent Containment isolation Ability todetermine and/or interpret the following asthey apply toINADVERTENT CONTAINMENT ISOLATION: Reactor water level Proposed Question: #83 The plant isatng@wn for arefueling outage with the following:
| |
| * RHR loopBisin aShutdown Cooling Lineup.
| |
| * No RWR pumps are running.
| |
| * Reactor water levelis210inches andstable.
| |
| * Maintenance isinprogress which hasthepotential for drainingtheReactor vessel.
| |
| * Then, anerror during l&Ctesting results inaninadvertent PCIS Group 2isolation.
| |
| * TheisolationCANNOT beimmediatelyrestored.
| |
| Which one ofthe following describes the response that isrequired tobedirected?
| |
| A Verify per isolations AOP-15,isolation Verification andRecovery. AOP-30, Loss of Shutdown Cooling, does NOTneed tobe entered.
| |
| B. Verify isolationsperAOP-15, Isolation Verification and Recovery. Enter AOP-30, Loss ofShutdown Cooling. Raise Reactor water level to between 234.5 and270Inches or start anRWRpump. Secure andrestore from themaintenance which has the potentialfor draining the Reactor vessel.
| |
| C. Verify isolationsperAOP-15, isolation Verificationand Recovery. Enter AOP-30, Loss ofShutdown Cooling. Secure andrestore from themaintenance which hasthe potential for draining theReactor vessel. Reactor water level does NOT need toberaised NORdoesaRWRpump needtobestarted.
| |
| D. Verify isolationsper AOP-15, isolation Verification andRecovery Enter AOP-30, Loss ofShutdown Cooling. Raise Reactor water level tobetween 234.5 and 270 inches or start anRWRpump. Themaintenance which hasthe potential fordrainingthe Reactor vessel maycontinue aslong asReactor water level controlis adequate.
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 1 Group # 1 K/A# 295023 AA2.03 Importance Rating3.8 Refueling Accidents Ability todetermine and/or interpret thefollowing asthey apply toREFUELING ACCIDENTS: Airborne contamination levels Proposed Question: #77 Theplant isoperating at100%power with the following:
| |
| ISFSI cask loading activities are inprogress.
| |
| a Anirradiated fuel bundle isdropped.
| |
| a 17RM-456A, Refuel Floor Exhaust Radiation Monitor, indicates 3x104 cpmandstable for over anhour.
| |
| a 17RM-456B, Refuel Floor Exhaust Radiation Monitor, indicates 8x103 cpmandstable for over anhour.
| |
| Which oneofthe following identifies whether anUnusual Event and/or Alert isrequiredtobe declared, inaccordance with EP-AA-1014 EALWallboard?
| |
| Declare anUnusual Event? Declare an Alert?
| |
| A. No No B. No Yes C. Yes No D. Yes Yes
| |
| | |
| Proposed Answer: B Explanation: Thegiven airborne contamination level on17RM-456A isabovetheHi-Hi setpoint(1x104 cpm) fortheRefuel Floor Exhaust radiation monitors anddue todamageto irradiated fuel. Therefore, Alert EALRA2ismetandmustbedeclared. Unusual RU2is Event NOTmet,despite theunplanned ARMreading rise inTable R2,because it isnotdueto lowering water level.
| |
| A. Incorrect -
| |
| Alert EAL RA2 is metandmustbedeclared. Plausiblebecauseonlyoneofthe Refuel Floor Exhaust rad monitors is above the threshold andAlert EALRA1isNOT applicable for thegiven radiation monitors.
| |
| C.Incorrect -
| |
| Alert EALRA2 is met andmustbedeclared. Plausiblebecauseonlyoneofthe Refuel Floor Exhaust rad monitors isabove the threshold andAlert EALRA1isNOT applicable for thegiven radiation monitors. Unusual Event RU2isNOTmet, the despite unplanned ARMreading rise inTable R2,because it isnotduetolowering level.
| |
| water Plausible because itwould bemetifthe radiation level wasduetolowering waterlevel.
| |
| D.Incorrect -
| |
| Unusual Event RU2isNOT met, despite the unplanned ARMreadingrisein Table R2,because it isnot duetolowering water level.Plausible becauseit wouldbemetif the radiation level wasduetolowering water level.
| |
| Technical Reference(s): ARPs09-3-2-29 and 09-3-2-40, EP-AA-1014 Proposed references tobeprovided toapplicants during examination: HotEALMatrix Learning Objective: LP-AOP1.12 Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 1 Group # 1 K/A# 295018 AA2.02 Importance Rating3.2 Partial orCompleteLoss ofCCW Ability todetermine and/or interpret thefollowing asthey apply toPARTIAL OR COMPLETE LOSSOFCOMPONENT COOLING WATER: Cooling water temperature Proposed Question:#78 Theplant isoperating at100%power with a laketemperature of860F slowly.
| |
| andrising Considering thefollowing Technical Specifications:
| |
| * 3.7.1,Residual Heat Removal Service Water (RHRSW) System
| |
| * 3.7.2,Emergency Service Water (ESW) System and Ultimate Heat Sink (UHS)
| |
| Which oneofthe following identifies which ofthese Technical Specifications (TS),
| |
| if any, currently Condition require entry?
| |
| A. NEITHER TS3.7.1 NORTS 3.7.2 requires Conditionentry.
| |
| B. TS3.7.1 requires Condition entry, but TS3.7.2 does NOT.
| |
| C. TS3.7.2 requires Condition entry, but TS3.7.1 does NOT.
| |
| D. Both TS3.7.1 andTS3.7.2 require Condition entry.
| |
| | |
| Proposed Answer: C Explanation: Lake temperature>850F exceeds theSurveillance Requirement3.7.2.2, therefore Condition entry isrequired for Technical Specification 3.7.2. RHRSW alsoultimately requires an acceptable lake temperature for proper operation, however Technical Specification 3.7.1 bases specifically doNOTrequire Condition entry for Technical Specification based 3.7.1 onlake temperature (credit is taken forCondition entry inTechnical 3.7.2).
| |
| Specification A. Incorrect -
| |
| TS3.7.2 requires Conditionentry because lake temperature is>850F. Plausible because this wouldbe correct if laketemperature were just slightlylower.
| |
| B.incorrect -
| |
| TS3.7.1 Condition entry isnotrequired. Plausible becauseelevated lake temperature does impactRHRSW performance. TS3.7.2 requires Conditionentrybecause lake temperature is>850F.Plausible becausethis would becorrect if lake were temperature just slightly lower.
| |
| D. Incorrect -
| |
| TS3.7.1 Condition entry isnot required. Plausible becauseelevated lake temperature does impact RHRSW performance.
| |
| Technical Reference(s): Technical Specifications 3.7.1 andassociated and3.7.2, bases Proposed references tobeprovided toapplicants during examination: Technical Specifications 3.7.1 and3.7.2, SR with 3.7.2.1 and3.7.2.2 allowable values removed Learning Objective: SDLP-46B 1.17 Question Source: Bank 16-1 NRC#90 Question History: 16-1NRC#90 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(2)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 1 Group # 1 K/A# 295030 2.2.38 Importance Rating4.5 LowSuppression Pool Water Level Knowledge ofconditions and limitations inthefacility license.
| |
| Proposed Question: #79 Theplant isoperating at100%power with the following:
| |
| a It isdiscovered thatthesurveillance for Torus water level(Surveillance Requirement (SR) 3.6.2.2.1)waslast performed 36 hours ago.
| |
| a TheSurveillance Frequency Control Program gives thefrequency SR3.6.2.2.1 for as24 hours.
| |
| a A risk evaluation hasbeen performed andthe associated impact isbeing managed.
| |
| Which oneofthe following describes the status ofLCO3.6.2.2, Suppression Pool Water Level, inaccordance withTechnical Specifications?
| |
| A. LCO3.6.2.2 mustbedeclared NOTmetimmediately.
| |
| B. Complete SR3.6.2.2.1 within a maximum of2 hours fromthe time ofdiscovery orthen LCO3.6.2.2 mustbedeclared NOTmet.
| |
| C. Complete SR3.6.2.2.1 within a maximum of6 hours fromthe time ofdiscovery or then LCO3.6.2.2 mustbedeclared NOTmet.
| |
| D. Complete SR3.6.2.2.1 within a maximum of24hours from thetime ofdiscovery orthen LCO3.6.2.2 mustbedeclared NOTmet.
| |
| | |
| Proposed Answer: D Explanation: Surveillance Requirement (SR) 3.0.3 applies given discoveryofa missed surveillance after the required frequency haselapsed. Therequirement todeclare LCOnot the metmaybedelayed, from the time ofdiscovery, upto24hours oruptothe ofthe limit specified frequency (in this case, also 24hours), whichever isgreater. Therefore upto24hours are allowed toperform the missed surveillancebefore being required todeclare theLCOnotmet.
| |
| A. Incorrect -
| |
| SR3.0.3 allows adelay time toperform the missed surveillance being before required todeclare the LCO not met.Plausible because themissed isover surveillance the 25%grace time allowed by SR 3.0.2.
| |
| B. Incorrect -
| |
| SR3.0.3 allows the longer of 24hours orthespecified (also frequency 24 hours). Plausible because 2 hours isthe c ompletion time of LCO Condition 3.6.2.2 A.
| |
| C.Incorrect -
| |
| SR3.0.3 allows thelonger of24hours orthe specified frequency (also 24 hours). Plausible because 6 hours is the grace time that would beallowed SR3.0.2 under (25% of24hours).
| |
| Technical Reference(s): Technical Specifications 3.6.2.2 andSR3.0.3 Proposed references tobeprovided toapplicants during examination: Technical 3.6.2.2 Specification Learning Objective: SDLP-16A 1.18 Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(1)
| |
| Comments:
| |
| | |
| ES-401 Written ExaminationQuestion Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier
| |
| # 1 Group # 1 K/A# 295037 EA2.01 Importance Rating4.3 Scram Condition Present andReactorPowerAboveAPRMDownscale orUnknown Ability todetermine and/or interpret thefollowing asthey apply toSCRAM CONDITION PRESENT ANDREACTOR POWER ABOVE APRMDOWNSCALE ORUNKNOWN: Reactor power Proposed Question: #80 Theplant wasoperating at100%power when a spurious Group 1Primary Containment isolation resulted signal inthe following:
| |
| a TheReactor ModeSwitch isinSHUTDOWN.
| |
| a Allcontrol rods are NOTfull in.
| |
| a APRMsare unavailable.
| |
| TwoSRVsare open.
| |
| a Torustemperature isabove theBoronInjection initiation Temperature.
| |
| a Reactor pressure is1138 psig andsteady.
| |
| a Reactorwater level is100" andslowly lowering.
| |
| a RCICandHPCIareNOTrunning.
| |
| Which oneofthe following describes the value current ofReactor power andthe required control ofReactor water level, inaccordance with EOP-3, Failure toScram?
| |
| Reactor power is...
| |
| A. 510%. Reactor water level mustbelowered further.
| |
| B. 510%.Reactor water level maybemaintained atthecurrent level.
| |
| C. >10%.Reactor water level must belowered further.
| |
| D. >10%.Reactor water level maybemaintained atthe level.
| |
| current
| |
| | |
| Proposed Answer: C Explanation: A Group 1isolation signalcauses theMSIVs toclose. Whenthe MSlVsarenot fullopen, a Reactor Scram isgenerated. EachSRVwill pass approximately900,000Ibm/hr at 1145 psig. Therefore 2 SRVs= 1.8 x 10e Ibm/hr. Total Steam Flow at100%power is approximately 10.97 x 106 Ibm/hr; therefore each SRVcanpass approximately 8.2%Rxpower.
| |
| TwoSRVsmultiplied by8.2%is~16%.With HPCIandRCICnotrunning, there arenoother steam loads sincethe MSlVs are shut. With Reactor power >2.5%, Reactor waterlevel
| |
| >0",
| |
| Torus temperature above BIIT, and anSRVopen, Reactor water levelmustbelowered further.
| |
| A. Incorrect -
| |
| Reactor power is >10%. Plausible because thiswould if only becorrect one SRVwasopen.
| |
| B. Incorrect -
| |
| Reactor power is >10%. Plausible because thiswould if only becorrect one SRVwasopen. Reactor water level must belowered further. because Plausible this would becorrect if Reactor power was<2.5%, Reactor water level was<0", Torus temperature wasbelow BIIT,orifnoSRVswereopen.
| |
| D. Incorrect -
| |
| Reactor water level must be lowered further.Plausible because would this be correct if Reactor power was<2.5%, Reactor water level was<0", Torus was temperature below BIIT, orifnoSRVswere open.
| |
| Technical Reference(s): FSARTable 4.4-1 and Chapter EOP-3 16.9.2, Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11d EO-1.07 Question Source: Modified Bank NMP12017 NRC#89 Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(5)
| |
| Comments:
| |
| | |
| SRVs Knowledge ofthe emergencyaction level thresholds andclassifications.
| |
| ProposedQuestion: #89 Theplant operating at100%
| |
| is power whenspurious isolationofboth Main lines Steam results inthe following:
| |
| = TheReactor Mode Switch has been placedinSHUTDOWN.
| |
| = Multiple control rods remain withdrawn.
| |
| = APRMs areunavailable.
| |
| = OneEmergency Cooling loop isinservice.
| |
| = Theother Emergency Cooling loop has failed toinitiate.
| |
| = OneERVis open.
| |
| = Reactor pressure is1080 psigand stable.
| |
| = Reactor water levelis72" andstable.
| |
| Which oneofthe following describes the requiredcontrol ofReactorwater inaccordance level, with theEmergency Operating Procedures, andthe highest EmergencyAction Level (EAL)that ismetorexceeded?
| |
| Reactor waterlevel..
| |
| A. must belowered. Thehighest EALmetorexceeded isanAlert.
| |
| B. must belowered. Thehighest EALmetorexceeded isaSite AreaEmergency.
| |
| C. maybemaintained atthe current level. Thehighest EALmetorexceeded is anAlert.
| |
| D. maybemaintained atthe current level. Thehighest EALmetorexceeded isa Site Area Emergency.
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 1 Group # 1 K/A# 295004 AA2.03 Importance Rating2.9 Partial orCompleteLoss ofD.C. Power Ability todetermine and/or interpret thefollowing asthey apply toPARTIAL OR COMPLETE LOSSOFD.C.POWER: Batteryvoltage Proposed Question: #81 Theplant isoperating at100%power with the following:
| |
| * 125VDCStation Battery Charger 71BC-1B isremoved from servicefor maintenance.
| |
| * Then, Temporary Battery Charger 71BC-9 is placed in service onBattery BusB.
| |
| * Theassociated Battery Busvoltage is131VDC and stable.
| |
| Which oneofthe following identifies thecurrent need for Condition entry into Technical Specification 3.8.4,DCSources -
| |
| Operating, andTechnical Specification 3.8.7, Distribution Systems -
| |
| Operating?
| |
| Technical Specification 3.8.4, TechnicalSpecification 3.8.7, M M A. Condition entry required. Condition entryrequired.
| |
| B. Condition entry required. Condition NOTrequired.
| |
| entry C. Condition entry NOTrequired. Condition entry required.
| |
| D. Condition entry NOTrequired. Condition NOTrequired.
| |
| entry
| |
| | |
| Proposed Answer: B Explanation: TS3.8.4 requires both the battery terminal voltage 2127.8VDCandthe125VDC battery charger inservice andcapable ofsupplying 2270 amps. Whilethe battery temporary charger may maintain busvoltage, itdoes not satisfy therequirements ofTS3.8.4.Therefore, TS3.8.4 Condition A mustbeentered. TS3.8.7 remains satisfied becausetheassociated bus isstillenergized to the appropriate voltage andcapable ofsupplying the loads.
| |
| required A. Incorrect -
| |
| TS3.8.7 condition entry isnotrequired. Plausible becausethe capacity current ofBattery BusB ismuch lower with 71BC-9 inservice (150 amps) andentry wouldbe required if voltage lowered asa result.
| |
| C. incorrect -
| |
| TS3.8.4 condition entry is required. Plausible because the battery temporary charger isplaced inserviceand ismaintaining busvoltage. TS3.8.7 condition isnot entry required. Plausible because the current capacityof Battery BusB ismuchlower with 71BC-9inservice (150amps) and entry would be required ifv oltage as lowered a result.
| |
| D. Incorrect -
| |
| TS3.8.4 condition entryis required. Plausible because the battery temporary charger isplacedservice maintaining busvoltage.
| |
| in and is Technical Reference(s): OP-43A, Technical Specifications 3.8.4 and3.8.7 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-71B EO-1.16 Question Source: Bank 17-1 NRC#81 Question History: 17-1 NRC#81 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(2)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier# 1 Group # 1 K/A# 295038 2.4.20 Importance Rating4.3 High Offsite Radioactivity Release Rate Knowledge oftheoperational implications ofEOPwarnings, cautions, andnotes.
| |
| Proposed Question: #82 Theplant hasexperienced anaccident with the following:
| |
| ThePrimary Containment Pressure Limit (PCPL) is being challenged.
| |
| PrimaryContainment venting would be necessary toprevent exceeding PCPL.
| |
| Which oneofthe following describes:
| |
| (1) whetherdefeating interlocks isallowed tovent thePrimary Containment and (2) whetherexceeding offsite radioactivity release limits rate during venting isallowed, inaccordance with EOP-4, Primary Containment Control?
| |
| M A. Allowed Allowed B. Allowed NOTallowed C. NOTallowed Allowed D. NOTallowed NOTallowed
| |
| | |
| Proposed Answer: A Explanation: EOP-4 allows both defeating interlocks andexceeding radioactivity offsite releaserate limits during venting toavoid exceeding PCPL.
| |
| B. Incorrect Exceeding offsite radioactivity release ratelimitsduring venting isallowed to avoid exceeding PCPL. Plausible because thereare other situations intheEOPswhere exceeding release rate limits isnot allowed.
| |
| C. Incorrect -
| |
| Defeating interlocks isallowed venting for toavoid exceeding PCPL.Plausible because there are other situations intheEOPswhere defeating interlocks isnotallowed.
| |
| D.Incorrect -
| |
| Defeating interlocks isallowed venting for toavoid exceeding PCPL.Plausible because there are other situations intheEOPswhere defeating interlocks isnotallowed.
| |
| Exceeding offsite radioactivity release rate during limits venting isallowed toavoid exceeding PCPL.Plausible because thereare other situations EOPswhere inthe exceeding release rate limits isnot allowed.
| |
| Technical Reference(s): EOP-4 Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11e EO-4.07 Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.43(5)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 1 Group # 2 K/A# 295033 EA2.03 Importance Rating 4.2 High Secondary Containment AreaRadiation Levels Ability todetermine and/or interpret thefollowing asthey apply toHIGHSECONDARY CONTAINMENT RADIATION AREA LEVELS: of tCause area high radiation Proposed Question: #83 Theplant isoperating at100%power with the following:
| |
| a A seismic event hasoccurred.
| |
| a Multiple barrels ofradioactive waste have spilled in theReactor Building.
| |
| a 18RIA-051-25, East HCUArea ARM,isinalarm andindicates upscale mr/hr).(>1x103
| |
| * 18RIA-051-26, WestHCUArea ARM,isinalarm and indicates upscale (>1x103 mr/hr).
| |
| Which oneofthe following describes therequired control ofthe Reactor, inaccordancewith the Emergency Operating Procedures?
| |
| A. TheReactor maycontinue tooperate atthe currentpower level.
| |
| B. A Reactor shutdown isrequired, but a Reactor scram isNOTrequired.
| |
| C. A Reactor scram isrequired, but anemergency RPVdepressurization isnot required.
| |
| D. A Reactor scram andemergency RPVdepressurization arerequired.
| |
| | |
| Proposed Answer: B Explanation: Thehigh ARMindications require entry EOP-5, into Containment Secondary Control. The ARMs areindicating thattwoMaxSafe levels radiation have (>103 beenexceeded mr/hr). Since the high area radiation levels are from leakingbarrels ofradioactive this material, isa non-primary system discharge. Therefore, EOP-5 requires a Reactor shutdown.EOP-5 would only require a Reactor scram andemergency RPVdepressurization if theseradiation levels were caused by a primary system discharge.
| |
| A. Incorrect -
| |
| EOP-5 requires a Reactorshutdown. Plausiblebecause thesource ofthe radiation levelsisnotconnected totheReactor. plausible Also becausethis wouldbe correct ifonly onearea exceeded theMaxSafe value.
| |
| C.Incorrect -
| |
| A Reactor scramis not required. Plausible because thiswould if becorrectthe radiation levelswere caused by a primary system discharge andonly onewasaboveMax Safe.
| |
| D.Incorrect -
| |
| A Reactor scram andanemergency RPVdepressurization isNOTrequired.
| |
| Plausible because this would becorrect if the radiation levels were causedbyaprimary system discharge.
| |
| Technical Reference(s): EOP-5 Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11f EO-1.07 Question Source: Modified Bank 16-1 NRC#85 Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(5)
| |
| Comments:
| |
| | |
| SecondaryContainment High Sump/Area Water Level Ability todetermine and/or interpret the following asthey apply toSECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Cause ofthe high level water Proposed Question: #85 Theplant is operating at 100% power with the following:
| |
| * A seismic event has occurred.
| |
| * The OBE EXCEEDED lightisNOTlit atthe Seismic Monitoring Panel.
| |
| * East Crescent area water level is26" andrising slowly.
| |
| * West Crescent area water levelis 20" andrising slowly.
| |
| * Torus water level is13.7' and lowering very slowly.
| |
| * Attempts toisolate the leakhave been unsuccessful.
| |
| * Anoperator has been directed to add water tothe Torus,but has NOTyetcompleted thisaction.
| |
| Which one of the following describes the required control oftheReactor, inaccordancethe with Emergency Operating Procedures?
| |
| A. TheReactor maycontinue tooperate atthe current power level.
| |
| B. A Reactor shutdown isrequired, but aReactorscram is NOTrequired.
| |
| C. AReactor scram isrequired, butanemergency RPV depressurization is required.
| |
| not D. AReactor scram andemergency RPVdepressurization are required.
| |
| JAF16-1 NRC
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 1 Group # 2 K/A# 295014 2.1.7 importance Rating4.7 inadvertent Reactivity Addition Ability toevaluate plant performance andmakeoperational judgments based on operating characteristics, reactor behavior, andinstrument interpretation.
| |
| Proposed Question: #84 Theplant isoperating at100%power with the following:
| |
| a A controlrod driftsfrom position 00to48 and CANNOT bere-inserted.
| |
| Reactorpower reaches a maximum of102% during thetransient.
| |
| Operators have lowered Reactor power to75%.
| |
| MCPRreached a low of1.05 during thetransient.
| |
| a MCPRisnow1.25.
| |
| Which oneofthe following describes theneed for afurther Reactor power reduction andthe need tomakeanENSnotification tothe NRC,inaccordance with Technical Specifications and LS-AA-1110, Exelon Reportability Reference Manual?
| |
| Further Reactor power reduction is .(1)ENSnotification tothe NRCis (2). .
| |
| A. required required B. required NOTrequired C. NOTrequired required D. NOTrequired NOTrequired
| |
| | |
| I Proposed Answer: A Explanation: MCPR<1.08, even for justashort period oftime, ofSafety isa violation Limit 2.1.1.2.Given theSafety Limit violation, Technical Specifications require inserting all insertable control rods within 2 hours. LS-AA-1110 requires ENSnotification oftheNRCduetoa shutdown required byTechnical Specifications.
| |
| B. Incorrect -
| |
| ENS notification oftheNRCisrequired. Plausible because there isnospecific 10CFR50.72 reporting requirement for a Safety Limit violation.
| |
| C. Incorrect -
| |
| Further power reduction isrequired. Plausible because therequired power reduction inAOP-27 has been satisfied and MCPRraised enough compliance torestore with theSafety Limit.
| |
| D. incorrect -
| |
| Further power reduction is required. Plausible because the required power reduction inAOP-27 hasbeensatisfied andMCPRraised enough compliance torestore with the Safety Limit. ENSnotification oftheNRCisrequired. Plausible because there is nospecific 10CFR50.72 reporting requirement for a Safety Limit violation.
| |
| Technical Reference(s): Technical Specification 2.0, LS-AA-1110 Proposed references tobeprovided toapplicantsduring examination: None Learning Objective: SDLP-02G 1.14 Question Source: BankSSESLOC27NRC#85(2015)
| |
| Question History: SSESLOC27 NRC#85(2015)
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content: 55.43(1 & 2)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 1 Group # 2 K/A# 295010 AA2.01 Importance Rating3.8 HighDrywell Pressure Ability todetermine and/or interpret thefollowing asthey apply toHIGHDRYWELL PRESSURE: tLeak rates Proposed Question: #85 Theplant isoperating at100%power with the following:
| |
| A leakhasdeveloped inthe Drywell.
| |
| * InputtotheDrywell Floor Drain sumps has risen from 0.3gpmto3.8 gpminthe last hour.
| |
| Drywellpressure is1.9 psig andstable.
| |
| Drywelltemperature is1300F andstable.
| |
| Note: Assume the leak rate remains constant andNOfurther information becomes available about the source ofthe leak.
| |
| With oneofthe following describes the need for a plant shutdownif thisleakage remains atthis level, inaccordance with Technical Specifications?
| |
| Technical Specifications...
| |
| A. doNOTrequire a plant shutdown.
| |
| B. requirea plant shutdown. Theplant mustbeplaced inMode3within a maximum of12 hours.
| |
| C. requirea plant shutdown. Theplant mustbeplaced inMode3within a maximum of16 hours.
| |
| D. requirea plant shutdown. Theplant mustbeplaced inMode3within a maximum of40 hours.
| |
| | |
| I Proposed Answer: C Explanation: Technical Specification 3.4.4requires s2gpmrise leakage inunidentified ina 24 hour period. Since unidentified leakage hasrisen by3.5 gpminasingle hour,theTechnical Specification limit has been exceeded. Thisrequires entry intoConditionB,whichallows 4
| |
| hours toattempt toreduce theleakage. After this4 hours, Condition Cmustbeentered,which allows 12hoursto enter Mode3,for a total of16hours.
| |
| A. incorrect -
| |
| A plant shutdown isrequired. Plausible because unidentified remains leakage below the limitof5gpm. Also plausiblebecause this would becorrect additional if information wasgiventhat the source oftheleakage wasnotservice sensitive 304or type type 316austenitic stainless steel.
| |
| B. Incorrect -
| |
| A maximum of16 hours isallowed.Plausible because would this becorrectif evidence weregiven that thisis pressure boundaryleakage.
| |
| D. Incorrect -
| |
| A maximum of16hours is allowed. Plausible because this isthe time correct for entering Mode4.
| |
| Technical Reference(s): Technical Specification 3.4.4 Proposed references tobeprovided toapplicantsduring examination: Technical 3.4.4 Specification Learning Objective: SDLP-02A 1.17 Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(2)
| |
| Comments:
| |
| | |
| ES-401 WrittenExamination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 2 Group # 1 K/A# 262001 A2.06 Importance Rating2.9 AC Electrical Distribution Ability (a) to predict DISTRIBUTION; and(b) theimpacts ofthefollowing ontheA.C.
| |
| based on those predictions,use ELECTRICAL procedures tocorrect,control, ormitigate theconsequences of those abnormal conditions oroperations: De-energizing a plant bus Proposed Question: #86 Theplant isoperating at100%power withthe following:
| |
| * A report hasbeen receivedofsmoke coming from MCC-253.
| |
| * TheUnit Supervisor hasdirected opening thesupply breaker tode-energize MCC-253.
| |
| Which oneofthe following identifies a loadthat will lose power as a resultof operation this and thecorrect implementation ofTechnical Specifications (TS)?
| |
| Load TSImplementation A. Standby GasTreatment Enter TS3.8.7, Distribution Systems -
| |
| Operating, FanA Condition A B. ControlRoomEmergency Enter TS3.8.7, Distribution SystemsOperating, Ventilation FanA Condition A C. Standby GasTreatment Enter TS 3.6.4.3,Standby GasTreatment (SGT)
| |
| FanA System, Condition A D. ControlRoomEmergency Enter TS3.7.3, Control RoomEmergency Ventilation Ventilation FanA Air Supply (CREVAS) System, Condition A
| |
| | |
| Proposed Answer: D Explanation: De-energizing MCC-253 results inloss ofpower toControl RoomEmergency Ventilation Fan A.TechnicalSpecification 3.8.7bases only require condition for entry loss of upstreamelectrical buses (L-25 or 10500),
| |
| butn otfor just loss of the MCC. R individual ather, system Technical Specifications areentered forthis power loss, including Technical Specification 3.7.3 Condition A for lossofoneControl RoomEmergency Ventilation Fan.
| |
| A. Incorrect -
| |
| Standby Gas Treatment FanA does notlose power. Plausible becausethis would becorrect for loss ofMCC-151. Technical Specification 3.8.7bases donotrequire condition entry for lossof this MCC. Plausible because this would becorrect for lossofthe upstream electrical board.
| |
| B.Incorrect -
| |
| Technical Specification 3.8.7bases donotrequire condition for entry lossofthis MCC.Plausible because thiswould becorrect for loss oftheupstream electrical L-board, 25.
| |
| C. Incorrect -
| |
| Standby GasTreatmentFan A doesnotlose power. Plausible becausethis would becorrect for loss ofMCC-151.
| |
| Technical Reference(s): AOP-18B,Technical Specification 3.8.7 andbases, TechnicalSpecification 3.7.3 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-70 1.10.a Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.43(2)
| |
| Comments:
| |
| | |
| ES-401 Written Question Examination Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier
| |
| # 2 Group# 1 K/A# 2030002.1.31 Rating4.3 Importance RHR/LPCI: Injection Mode Ability tolocatecontrolroom switches, andtodetermine andindications, controls, that they correctlyreflectthedesired plantlineup.
| |
| | |
| Proposed Question: #87 Theplant has experienced a small coolant leak inthe with Drywell following:
| |
| the
| |
| = The Reactor isscrammed.
| |
| a A cooldown iscommenced.
| |
| = Injectionfrom Core Spray andRHRisterminated andprevented.
| |
| a TheRHRgrayboot connectors are disconnectedper Termination EP-5, andPrevention ofRPVinjection.
| |
| * RHRA isaligned as shown onthenext page.
| |
| = RHRB isNOTavailable.
| |
| Then, the coolant leakdegradesand results inthe following:
| |
| = Reactor water level is80" andslowly lowering.
| |
| * Reactor pressure is750psig andslowly lowering.
| |
| a Drywell pressure is14psig andslowly lowering.
| |
| * Thealternate levelcontrol leg ofEOP-2, RPV Control, hasbeen entered.
| |
| * Both Core Spray systems areavailable.
| |
| a AllCondensate Booster pumps areavailable.
| |
| Which oneofthe followingdescribes:
| |
| (1) the required control ofRHRA sprays and (2) therequired control of10MOV-27A, LPCIOUTBDINJVLV, inaccordance with theEmergency Operating Procedures?
| |
| 10MOV-27A A. Maybeleft inthecurrent lineup Maybeleft inthe position current B. Maybeleft inthecurrent lineup Mustberepositioned C. Mustberealigned inthecurrent Maybeleft position D. Must berealigned Mustberepositioned
| |
| | |
| > r '
| |
| '=' '
| |
| y :;=:,.
| |
| e--y x j ) "
| |
| j " "
| |
| , f .
| |
| k y
| |
| j l gf '
| |
| Q l j /f) a% (y j. v' m
| |
| 'r i
| |
| /
| |
| / ,
| |
| r;m>
| |
| y f
| |
| <f ; l3 ?e.f
| |
| . f /
| |
| c 4,;.:
| |
| R M .
| |
| M ..
| |
| W .
| |
| M.. M
| |
| | |
| Proposed Answer: A Explanation: Thegiven indications showthat the RHRA sprays areinserviceand10MOV-27Aisclosed aspart ofanearlier terminate/prevent. Reactor water level islowering butstill above thetop ofactive fuel. Thealternate level controllegofEOP-2 isapplicable, aswellas EOP-4. UntilReactor water level drops totopofactive fuel, there isnorequirementtorealign 10MOV-27A forinjection. Additionally, there isnorequirement totake RHRA outofsprays prior toreaching top of active fuel.
| |
| B.Incorrect -
| |
| There isno requirement torealign 10MOV-27A for Plausible injection. because this maybecome required if Reactor water levellowersfurther.
| |
| C.Incorrect -
| |
| There isnorequirement totake RHRA outofsprays. Plausible because Drywell pressure hasalready beensignificantly lowered bysprays andReactor waterlevel is continuing tolower, which mayrequire LPCI injection.
| |
| D.Incorrect -
| |
| There isnorequirement to take RHRA outofsprays. Plausible because Drywell pressure hasalready beensignificantly lowered bysprays andReactor waterlevel is continuing tolower, which mayrequireLPCI injection. There isnorequirementtorealign 10MOV-27A for injection. Plausible because this maybecome requiredReactor if water level lowers further.
| |
| Technical Reference(s):EOP-2, EOP-4,EP-5 Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: MIT-301.11c 1.05 Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(5)
| |
| Comments:
| |
| | |
| ES401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 2 Group # 1 K/A# 211000 A2.01 Importance Rating3.8 Standby LiquidControl Ability SYSTEM; (a) to predict and(b) theimpacts ofthefollowing based onthose predictions, ontheSTANDBY use procedures to LIQUID correct, CONTROL or control, mitigate theconsequences of those abnormal conditions oroperations: Pumptrip Proposed Question: #88 Theplant hasexperienced afailure toscram with thefollowingsequence ofevents:
| |
| Time(minutes) Condition(s) 0 a Reactor power is25%.
| |
| * Reactor pressure is920psig.
| |
| 3 a Standby Liquid Control (SLC) pump A is started.
| |
| a InitialSLCtank level is90%.
| |
| 30 a SLCpumpA trips.
| |
| * AnOperator attempts tostartSLCpumpB.
| |
| a SLCpumpB fails tostart.
| |
| 32
| |
| * AIIAPRMsnowindicate downscale.
| |
| a AllIRMsindicate mid-scale onrange 3.
| |
| a Multiple controlrods remainfullywithdrawn.
| |
| Note: Assume SLCpumpA operated atexactly thedesign flow rate.
| |
| Which oneofthe following describes theability tocommence a Reactor cooldown,in accordance withEOP-3, Failure toScram?
| |
| A Reactor cooldown iscurrently...
| |
| A. allowedbased onReactor power indications.
| |
| B. allowedbased ontheamount ofboron injected.
| |
| C. NOTallowed because Reactor power istoohigh.
| |
| D. NOTallowed because oftheamount ofboron injected.
| |
| | |
| Proposed Answer: D Explanation: SLCpumpA injected for 27minutes at50gpm, which results of1350 ininjection gallons of boron solution. This will result inafinaltank levelofapproximately oftank (a
| |
| 63% 27%
| |
| reduction).This is greater than thehot shutdown boron weight (26% level),
| |
| but lessthan thecold shutdown boron weight (45% oftank level).With someboron EOP-3 injected, doesnot allowed cooldown until the cold shutdown boron weight isinjected. Therefore, cooldownisnot currently allowed due to theamountof boron injected.
| |
| A. Incorrect -
| |
| Reactor cooldown isnotcurrently allowed. Plausible becausea substantial amount ofboron hasbeen injected andpower haslowered significantly.
| |
| B.Incorrect -
| |
| Reactor cooldown isnot currentlyallowed. Plausible becauseasubstantial amount ofboron hasbeen injected and power haslowered significantly.
| |
| C.Incorrect -
| |
| Thereason isnot Reactor power. Plausible because Reactorpowerisstill not fully downscale ontheIRMs. Also plausible becausethis decision ismadebasedon Reactor power infoboron isinjectedyet.
| |
| Technical Reference(s):OP-17,EOP-3 Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11c 1.07 Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(5)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier# 2 Group # 1 K/A# 215005 A2.07 Importance Rating3.4 Average Power Range Monitor/Local Power Range Monitor Ability (a) to predict MONITOR/LOCAL theimpacts ofthefollowing POWERRANGE MONITOR SYSTEM; ontheAVERAGE and(b)
| |
| POWER based onthose RANGE predictions, useprocedures to correct, control,ormitigate theconsequences ofthose abnormal conditions oroperations: Recirculation flow channels flow mismatch Proposed Question: #89 A plant startupisinprogress with the following:
| |
| * TheReactor ModeSwitch isinSTART& HOT STBY.
| |
| e Recirculationflow unit A is failed upscale andbypassed.
| |
| a Then, Recirculation flow unit Cfails upscale.
| |
| Given the following:
| |
| e Technical Specification (TS) 3.3.1.1, Reactor ProtectionSystem (RPS) Instrumentation
| |
| * Technical Requirements Manual (TRM) 3.3.B,Control Rod Block Instrumentation Which oneofthe followingdescribes theneed for Condition entryinTS3.3.1.1 and/or TRM 3.3.B?
| |
| W A. No No B. Yes No C. No Yes D. Yes Yes
| |
| | |
| Proposed Answer: A Explanation: With both Recirculation flow unit A bypassed andC failed APRMsA,C, upscale, andE are provided a non-conservative Recirculation flow signal.This makes flow the biased scram function oftheseAPRMsinoperable. WiththeReactor ModeSwitch inSTART/HOT STBY, TS3.3.1.1 requires 2 operable APRMspertrip system toinitiateanupscaletrip s15%.
| |
| Theflow biased scram is not required tobeoperable. Therefore, TS3.3.1.1 isnot entry required. With the Reactor ModeSwitch inSTARTUP/HOT STANDBY, TRM3.3.B requires 4
| |
| operable APRMstoinitiate anupscalerod block 512%anda downscale rodblock 22.5%.The flow biased rod blockisnot required tobeoperable. Therefore, TRM3.3.B isnotrequired.
| |
| entry B. Incorrect -
| |
| TS3.3.1.1 entry isnotrequired. Plausible because this would if becorrectthe Reactor ModeSwitch wasin RUN.
| |
| C.Incorrect -
| |
| TRM3.3.B entry isnot required. Plausible because this would becorrectthe if Reactor ModeSwitch wasinRUN.
| |
| D.incorrect -
| |
| TS3.3.1.1 entry isnot required. Plausible because this would if becorrectthe Reactor ModeSwitch wasinRUN.TRM 3.3.B entry isnot required. Plausible becausethis would becorrect if theReactor ModeSwitch was inRUN.
| |
| Technical Reference(s): TS3.3.1.1, TRM 3.3.B Proposed references tobeprovided toapplicants during examination: TS3.3.1.1 andTRM (with 3.3.B allowable values removed)
| |
| Learning Objective: SDLP-07C 1.16 Question Source: Modified Bank 16-1 NRC#90 Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(2)
| |
| Comments:
| |
| | |
| ProposedQuestion: #88 A plant startup isinprogress with thefollowing:
| |
| a TheReactor ModeSwitch is inSTARTUP/HOT STANDBY.
| |
| * Thefollowingannunciators are all SJeg o 09-5-1-41, NEUTRON MONSYSTRIP o 09-5-2-2, RODWITHDRAWAL BLOCK o 09-5-2-34, APRMDOWNSCALE o 09-5-2-44, APRM UPSCALE o 09-5-2-54, APRMTRIP SYSA INOPORUPSCALE TRIP o 09-5-2-55, APRMTRIP SYSB INOPORUPSCALE TRIP
| |
| * APRMs indicate asfollows:
| |
| APRM Indication A 10%
| |
| B 18%
| |
| C 8%
| |
| D 18%
| |
| E 16%
| |
| F 10%
| |
| Given thefollowing requirements:
| |
| * Technical Specification (TS) 3.3.1.1, Reactor Protedion System (RPS) Instrumertation
| |
| * Technical Requirements Manual (TRM) 3.3.B, Control RodBlock Instrumertation Which oneofthefollowing describesthe needfor Condition entry inTS3.3.1.1and/or TRM 3.3.B?
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| . E .
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| g yp yg
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| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
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| | |
| ==Reference:==
| |
| Level SRO Tier # 2 Group # 1 K/A# 209001 2.4.9 Importance Rating4.2 LowPressure CoreSpray Knowledge oflowpower/shutdown (e.g.,
| |
| implications inaccident loss ofcoolant accident orloss ofresidual heat removal) mitigation strategies.
| |
| Proposed Question: #90 A plant startupisinprogress whena loss of coolant results accident inthe following:
| |
| * Reactorwater level is-19" andslowlylowering.
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| * Reactorpressure is210psig andslowlylowering.
| |
| * Core Spray pumps areinjecting.
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| Core Spray A flow is3500 gpm.
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| Core Spray Bflow is4200 gpm.
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| * NOother injectionsystems are available.
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| NOSRVshave beenopened.
| |
| * TheAlternate Level Control legofEOP-2, RPVControl,is being executed.
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| Which oneofthe following describes therequired action, inaccordancewith EOP-2?
| |
| A. ExittheEOPsandenter the SAOGs.
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| B. EntertheEmergency RPVDepressurization ofEOP-2.
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| leg C. Rapidlydepressurize theReactor using Turbine Bypass Valves.
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| D. Minimize steam loads andattempt tostabilize Reactorpressure.
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| | |
| Proposed Answer: B Explanation: Reactorwater levelisless than 0"andEmergency RPVDepressurization hasnot yet been performed, asevidences bynoSRVsbeing opened andthe given placeinEOP-2.
| |
| Reactor pressure islowenough for someCore Spray injection based onthelowstarting pressure ofthe Reactor startup andthe lossofcoolant accident, however moreCore Spray flow isavailable after Reactor pressure is loweredfurther. Based onthecurrent position inEOP-2 andthe given plant conditions, the required action istoenter theEmergency RPV Depressurization legof EOP-2.
| |
| A. Incorrect -
| |
| Exiting theEOPs andentering theSAOGsisnot currently Plausible required.
| |
| because this would becorrect if anEmergency RPVDepressurization hadalreadybeen performed andthe given combination ofReactor water level andCore Sprayflowswasstill present.
| |
| C.Incorrect -
| |
| Entering the Emergency RPV Depressurization leg ofEOP-2isrequired, not rapid depressurization with TBVs.Plausible because theallowance torapidly depressurize with TBVsisgiven inEOP-2andwould likely resultingreater Core Sprayflow.
| |
| D.Incorrect -
| |
| Entering theEmergency RPVDepressurization leg ofEOP-2isrequired.
| |
| Plausible because this isthestrategy thatwould beemployed ifNOinjection sourceswere available intheSteam Cooling leg.
| |
| Technical Reference(s):EOP-2 Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11b 1.07 Question Source: Bank NMP12018NRC#90 Question History: NMP12018NRC#90 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(5)
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| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination Outline Cross-
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| | |
| ==Reference:==
| |
| Level SRO Tier # 2 Group # 2 K/A# 290002 2.2.25 Importance Rating4.2 Reactor Vessel Internals Knowledge ofthebasesin Technical Specifications forlimiting conditions for operations andsafety limits.
| |
| Proposed Question: #91 Technical Specification RCSSpecific 3.4.6, Activity, limits theallowable specificactivity inthe Reactor coolant.
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| Which oneofthe following describes thelimitationand thebasis behind this limitation, in accordance with Technical Specifications?
| |
| Limits specificactivity ofdose equivalent . (.1.) intheReactor coolant toprevent exceeding 10CFRlimits during a designbasis (2)
| |
| (1) (2)
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| A. Cesium 137 Recircloop rupture B. Cesium 137 Main Steam Line break C. lodine131 Recirc loop rupture D. lodine131 Main Steam Line break
| |
| | |
| Proposed Answer: D Explanation: TS3.4.6 limits the dose equivalent I-131 specific toensure activity 10CFR that dose limits are not exceeding during a Main Steam Line break.
| |
| A. incorrect Dose equivalent I-131, notCs-137, islimited byTS3.4.6. Plausible because Cs-137isa significant radioisotope referenced inODCM.Thebasis thelimitation behind isa Main Steam Line break, not a Recirc loop rupture. Plausible becausea Recircloop rupture isthebasis for many plant limits.
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| B.Incorrect -
| |
| Doseequivalent I-131, notCs-137, islimited byTS3.4.6. Plausible because Cs-137isa significant radioisotope referenced in ODCM.
| |
| C. Incorrect -
| |
| Thebasis behind thelimitation is a Main Steam Line break, not loop a Recirc rupture. Plausible because Recirc a loop rupture is basis t he for manyplantlimits.
| |
| Technical Reference(s):Technical Specification 3.4.6 andBases Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: JLP-OPS-ITSO21.05 Question Source: Bank 14-2 NRC#94 Question History: 14-2 NRC#94 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.43(2)
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| Comments:
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| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier
| |
| # 2 Group# 2 K/A# 234000 A2.01 Importance Rating3.7 Fuel Handling Equipment Ability and(b)
| |
| (a) to predict basedonthose theimpacts ofthe predictions, followingontheFUELHANDLiNG useprocedurestocorrect, EQUlPMENT; ormitigate control, the consequences ofthose abnormal conditions oroperations:
| |
| interlock failure
| |
| | |
| Proposed Question: #92 A refueling outage isinprogress with thefollowing:
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| a The Reactor ModeSwitch isinREFUEL.
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| a A fuelbundle islatched onthe RefuelBridge mainhoist.
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| TheRefuel Bridge islocated over the center oftheReactor.
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| a TheRefuelBridge mainhoist isinthenormal-up position.
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| Then, the followingoccurs:
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| Controlrod 02-43 isinadvertently given awithdraw signal.
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| a Thecontrol rodblock interlock failsandcontrol rod02-43 withdraws toposition 06.
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| Which oneofthe following describes:
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| (1) whether another interlock exists thatshould prevent loweringthe fuelbundle intothe core, and (2) whether fuelmovements into thecore are allowed tocontinue with the failedcontrol rod block interlock, inaccordance with Technical Specifications?
| |
| (1)Doesanother interlock existthatshould prevent lowering thefuel bundle Into (2)Arefuel movements into the core allowed to thecore? continue with the controlrod block interlock?
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| failed A. No Yes, provided thatall including02-43, are rods, fully inserted andacontrol rodblock isinserted.
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| B. No No,the interlock mustbefixed before anyfuelcan be movedinto thecore.
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| C. Yes Yes,provided thatall including rods, 02-43, are fully inserted andacontrol rodblock isinserted.
| |
| D. Yes No,theinterlock mustbefixed before anyfuel canbe moved into thecore.
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| | |
| Proposed Answer: C Explanation: Thefuel movement will still beinterrupted byaninterlock before thefuelbundle canbeplaced into thecore. This interlock prevents lowering the main h oist while overt he core with afuel bundle with acontrol rodnot fully inserted. Technical Specification 3.9.1doesallow further fuel movement into thecore with thefailedinterlock, butonly all if control rodsarefully inserted andacontrol rod block isinserted.
| |
| A. Incorrect -
| |
| Thefuel movement will beinterrupted still byaninterlock before thefuelbundle canbeplaced into the core. Plausible because notall interlocks havesucha backup.
| |
| B. Incorrect -
| |
| Thefuel movement will still beinterrupted byaninterlock before thefuelbundle canbeplaced into the core. Plausible because not allinterlocks havesucha backup.
| |
| Technical Specification 3.9.1 does allow further fuel movement the into corewith thefailed interlock. Plausible becauseone ofthe Required Actions istoimmediately suspendin-vessel fuelmovements.
| |
| D. Incorrect -
| |
| Technical Specification3.9.1 does allow further fuel movementintothe with core the failed interlock. Plausible because one of theRequired Actions istoimmediately suspend in-vessel fuel movements.
| |
| Technical Reference(s): OP-66A, Technical Specification 3.9.1 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-08B 1.05.b.3 Question Source: Modified Bank 17-1 NRC#31 Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(7)
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| Comments:
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| | |
| Fuel Handling Equipment Knowledge ofthe operational implications ofthe following concepts asthey applyto FUEL HANDLING EQUIPMENT: Crane/hoist operation Proposed Question: #31 A refueling outage is inprogress with the following:
| |
| a TheReactor Mode Switch isinREFUEL a A fuel bundle islatched onthe Refuel Bridgemain hoist incenter oftheSpentFuelPool.
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| a TheRefuel Bridge main hoist isin thenormal-up position.
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| a Onecontrol rodis withdrawn toposition 04.
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| Which oneofthe following describes whehfuel movement would firstbeinterruptedbyan interlock if the Refuel Bridge Operator attempted toplace thefuel bundle inthecore?
| |
| This fuelmovement would firstbeinterrupted byaninterlock- .
| |
| A. assoon asany attempt ismadetomovethe Refuel Bridge towards thecore.
| |
| B. aftertheRefuel Bridge begins moving towards the core, but beforeitgetsabovethe core.
| |
| C. assoon asanyattempt ismadetolower the fuel bundle once overthecore.
| |
| D. whenthebottom ofthe fuel bundle isloweredenough toreach theheightofthecore top guide.
| |
| JAF1-1NRC
| |
| | |
| ES-401 Written Examination QuestionWorksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier# 2 Group # 2 K/A# 202002 2.2.40 importance Rating4.7 Recirculation FlowControl Ability toapply Technical Specifications for a system.
| |
| Proposed Question:#93 Theplant isoperatingat95%powerwith thefollowing:
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| * RecirculationpumpA flow hasspuriously drifted lower.
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| * RecirculationpumpA loop flow is32.3 MIbm/hr andstable.
| |
| a RecirculationpumpB loop flow is38.0 MIbm/hr andstable.
| |
| Considering thefollowing Technical Specifications:
| |
| * 3.4.1,Recirculation Loops Operating a 3.4.2,JetPumps Which oneofthe following identifies which ofthese Technical Specifications ia (TS), fny, currently Condition require entry?
| |
| A. NEITHER TS3.4.1 NORTS3.4.2 requiresCondition entry.
| |
| B. TS3.4.1 requires Condition entry, butTS3.4.2 doesNOT.
| |
| C. TS3.4.2 requires Condition entry, butTS3.4.1 doesNOT.
| |
| D. BothTS3.4.1 andTS3.4.2 require Condition entry.
| |
| | |
| Proposed Answer: B Explanation: Thegiven flows showgreater than 5%Recirculation jet loop pumpflowmismatch with total core flow>70%ofrated. This inUNSATperSurveillance Requirement 3.4.1.2 and requires Condition entry inTechnical Specification 3.4.1, but not 3.4.2.
| |
| A. IncorrectTechnical Specification 3.4.1 Condition entry isrequired. Plausible because mismatch is<10% and wouldnot requireCondition entry iftotal core was<70%of flow rated.
| |
| C.Incorrect -
| |
| Technical Specification 3.4.1 Condition entry isrequired. Plausible because mismatch is<10%andwould not requireCondition entry iftotal core was<70%of flow rated. Technical Specification 3.4.2 Conditionentry isNOTrequired. Plausible because other jet pump/Recirculation conditions dorequired entry into related this Technical Specification.
| |
| D. Incorrect -
| |
| Technical Specification 3.4.2 Condition entry isNOTrequired. Plausible because other jet pump/Recirculation conditions dorequired into entry related this Technical Specification.
| |
| Technical Reference(s): OP-27, Technical Specifications 3.4.1 and3.4.2 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-02H 1.16 Question Source: New Question History:
| |
| Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(2)
| |
| Comments:
| |
| : i ii.
| |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier# 3 Group #
| |
| K/A# 2.1.41 Importance Rating3.7 Knowledge oftherefueling process.
| |
| Proposed Question: #95 A refueling outage isinprogress.
| |
| Which oneofthe following Refuel Flooractivities must bedirectly supervised bya licensed Senior ReactorOperator (SRO), inaccordance with OSP-66.001, Management ofRefueling Activities?
| |
| A. Cleaning Recirc jet pumps inthe Reactor vessel.
| |
| B. Loadinganewfuel bundle into theSpent Fuel Pool.
| |
| C. Removing acontrol rod from acore cell containing fuel.
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| D. Moving LPRMstrings from the core tothe Spent FuelPool.
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| | |
| Proposed Answer: C Explanation: Removing acontrol rodblade from acore cellthat contains fuel meetsthe definition of a CoreAlteration. All Core Alterations mustbedirectly supervised bya licensed Senior Reactor Operator.
| |
| A. IncorrectThis does not required direct byanSRO.Plausible supervision becauseRecirc jet pumps arereactivity related components, soimproper maintenance could havea negative effect on reactivity management once theplant topower.
| |
| isreturned B. Incorrect -
| |
| This does not required direct byanSRO.Plausible supervision becauseloading anewfuel bundle intothe Reactor does require supervision direct byanSRO.
| |
| D. Incorrect -
| |
| This does notrequired direct byanSRO.Plausible supervision becauseLPRMs are aspecific exception discussed inOSP-66.001.
| |
| Technical Reference(s): OSP-66.001 Proposed references tobeprovided toapplicants duringexamination: None Learning Objective: LP-AP 73.03 Question Source: Bank Peach Bottom2017 NRC SRO#24 Question History: Peach Bottom 2017NRCSRO #24 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.43(6)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 3 Group #
| |
| K/A# 2.2.7 Importance Rating3.6 Knowledge oftheprocess for conducting special orinfrequent tests.
| |
| Proposed Question: #96 Planning isunderway for a Special Test orEvolution.
| |
| Given the following items:
| |
| (1) Assignment ofa specific Coordinator for the evolution.
| |
| (2) Infrequent Plant Activity briefing withparticipation bya Senior Line Manager.
| |
| (3) Continuous oversight of evolution byeither t he Plant Manager or Site Vice President.
| |
| Which oneofthe followingidentifies which ofthese items is specifically theSpecial for required Test orEvolution, inaccordance withOP-AA-108-110, Evaluation ofSpecial Tests or Evolutions?
| |
| A. (1) and(2) only B. (1) and(3) only C. (2) and(3) only D. (1), and(3)
| |
| (2),
| |
| | |
| Proposed Answer: A Explanation: OP-AA-108-110 requires assignment ofa specific Coordinator (called the SpecialTest orEvolution Coordinator) andconduct ofanInfrequent Plant Activity briefing with participation by a senior line manager. OP-AA-108-110 requires ensuring appropriate station management involvement ispresent during the evolution, but does notspecifically require continuous oversight bythe Plant Manager orSite Vice President.
| |
| B. Incorrect -
| |
| OP-AA-108-110 requires conduct ofanInfrequent PlantActivity briefing with participation bya senior linemanager. Plausible that a different levelofbriefing, suchasthe Heightened Level ofAwareness brief, would berequired, orthat lower level management involvement would beenough. OP-AA-108-110 requires ensuring appropriate station management involvement is present during the evolution, but does not specificallyrequire continuous oversight bythePlant Manager orSite Vice President. Plausible thehighest that level ofstation management would be required due tothe risk involved with theseevolutions andpast industry events.
| |
| C.Incorrect -
| |
| OP-AA-108-110 requires assignment ofaspecific Coordinator (called the Special Test orEvolution Coordinator). Plausible thatnormal Operations leadership (SM/US) would suffice duetotheir normal high level of responsibility for stationoperations.
| |
| OP-AA-108-110 requires ensuring appropriate station management involvement ispresent during the evolution, but does notspecifically require continuous oversight bythePlant Manager orSite Vice President. Plausible that thehighest level ofstation management would berequired duetotherisk involved with these evolutions andpast industryevents.
| |
| D. Incorrect -
| |
| OP-AA-108-110 requires ensuring appropriate station management involvement ispresent during the evolution, but does notspecifically require continuous bythe oversight Plant Manager orSite Vice President. Plausible that the highest level of station management would berequired duetothe risk involved with these evolutions andpast industry events.
| |
| Technical Reference(s): OP-AA-108-110 Proposed references tobeprovided toapplicants during examination: None Learning Objective:
| |
| Question Source: Bank NMP22014Cert
| |
| #95 Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.43(3)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier 3 Group #
| |
| K/A# 2.2.18 Importance Rating3.9 Knowledge oftheprocess for managing maintenance during activities shutdown operations, suchasrisk assessments, workprioritization, etc.
| |
| Proposed Question: #97 Theplant isshutdown for a refueling outage.
| |
| Which oneofthe following describes theminimum requirements for oftheoutage review risk assessment againstactual plant conditions,in accordance with Outage AP-10.09, Risk Assessment?
| |
| Atleast once per...
| |
| A. shift byaminimum oftwo(2) individuals B. shift byaminimum ofone(1) individual C. daybya minimum oftwo(2) individuals D. daybya minimum ofone(1) individual
| |
| | |
| Proposed Answer: A Explanation: AP-10.09 requires theSafety Shutdown Manager toverifythecurrent plant conditions are in compliance with theoutage risk assessment atleast onceeachshift.
| |
| AP-10.09 also requires a ShiftManager toindependently reviewthisverification atleast onceeach shift. Therefore, atleasttwo(2) individuals mustperform thereview.
| |
| B. Incorrect -
| |
| AP-10.09 requires the review bytwo(2) individuals.Plausible because thisis review ofanalready developed plan.
| |
| C. Incorrect -
| |
| AP-10.09 requires the review atleast oncepershift. Plausible many because reviews /surveillances are daily.
| |
| D. Incorrect -
| |
| AP-10.09 requires thereview atleast onceper shift.Plausible because many reviews /surveillances aredaily. AP-10.09 requires thereview bytwo(2) individuals.
| |
| Plausible because thisisreview of analready developed plan.
| |
| Technical Reference(s): AP-10.09 Proposed references tobeprovided toapplicants during examination: None Learning Objective: LP-AP 41.03b Question Source: Bank 14-2 NRC#95 Question History: 14-2 NRC#95 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.43(5)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES401-5 Examination OutlineCross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier# 3 Group #
| |
| K/A# 2.3.12 Importance Rating3.7 Knowledge ofradiological safetyprinciples pertaining tolicensed operator such duties, ascontainment entryrequirements, fuelhandling access responsibilities, tolockedhigh-radiation areas,aligning filters, etc.
| |
| Proposed Question: #98 Given the following categories offuel:
| |
| (1) Newfuel (2) Recently irradiated fuel (3) Irradiated fuelthat hasdecayed foratleast1 year Which oneofthe following identifies which ofthese may be stored intheperipheral rowofthe Spent Fuel if P ool, any, inaccordance withOSP-66.001,Management ofRefueling Activities?
| |
| A. None B. (3)only C. (1)and(3) only D. (2)and(3) only
| |
| | |
| I Proposed Answer: C Explanation: OSP-66.001 contains the following restriction:
| |
| 6.8.7 For fuel storedin the Spent Fuel Pool, the following requirements shall apply:
| |
| * Only new fuel, or fuel decayedfor 1 year or more, shallbe placed in the peripheral rows of the Spent Fuel Pool.
| |
| A. Incorrect -
| |
| Newfuel andfuel decayed for atleast oneyear maybestored intheperipheral rowoftheSpent Fuel Pool.Plausible that a restriction would allow inthis nostorage row duetoeither criticalityorradiation issues.
| |
| B. Incorrect -
| |
| Newfuel maybestored in the peripheral rowoftheSpent Pool.
| |
| Fuel Plausible that arestriction would notallow storage ofnewfuel duetocriticality issues.
| |
| D.Incorrect -
| |
| Newfuel maybestored inthe peripheral rowoftheSpent Fuel Pool.Plausible that a restriction would notallow storage of new fuel issues.
| |
| duetocriticality Recently irradiated fuel maynotbestored intheperipheral rowoftheSpent Fuel Pool. if Plausible the radiation streaming concern were notunderstood.
| |
| Technical Reference(s): OSP-66.001 Proposed references tobeprovided toapplicants during examination: None Learning Objective: SDLP-08A 1.13.b Question Source: New Question History:
| |
| Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.43(7)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-4015 Examination Outline Cross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 3 Group #
| |
| K/A# 2.4.18 Importance Rating4.0 Knowledge ofthespecific basesfor EOPs.
| |
| Proposed Question: #99 Theplant isinarefueling outage with the following:
| |
| a Theplant isinMode5.
| |
| a Anirradiated fuel bundle hasbeen dropped inthe Spent Fuel Pool.
| |
| * TheSpent Fuel Pool area radiationmonitor, 18RIA-051-12, hasexceeded theMaximum Normal reading but isbelow theMaximum Safe reading.
| |
| Which oneofthe following describes theentry requirement for EOP-5,Secondary Containment Control?
| |
| A. EOP-5 entry isrequired tolimitradioactivity release toand from theReactor Building.
| |
| B. EOP-5 entry isNOTrequired because the Reactor coolant system isina lowenergy state.
| |
| C. EOP-5entry isNOTrequired because thecause oftheentry condition is known andit is NOTa primary system discharging into the Reactor Building.
| |
| D. EOP-5 entry isNOTrequired because the bases doNOTaddress a droppedfuel bundle andassume such anaccident ishandled using AOP-44, Dropped Fuel Assembly.
| |
| | |
| Proposed Answer: B Explanation: Thegiven area radiation monitor condition meets anEOP-5 entrycondition.
| |
| However, EOP basesspecifically doNOTrequire theEOPstobeentered ifReactorcoolant temperature islessthan 2120F anda Reactor startup orshutdown isNOTinprogress. Since theplant isin Mode 5,Reactorcoolant temperature isless than 2120F,anda Reactor or startup shutdown isNOT inprogress. Therefore EOP-5entry isNOTrequired.
| |
| Note: While the question deals with EOPentry, it rises tothe SROlevel because itisnot straight memory ofEOP entry condition, but also knowledge ofbases behind EOPentry requirements ("knowledge of administrative procedures that specify hierarchy,implementation, and/or coordination ofplantnormal, abnormal, andemergency procedures").
| |
| A. Incorrect -
| |
| Since theplant isin Mode 5,Reactor coolant temperature isless than212oF and a Reactor startup orshutdown is NOT inprogress. Therefore EOP-5entry isNOTrequired.
| |
| C.Incorrect -
| |
| EOP-5 bases statethatthe purpose of thehigh area radiation levelentry condition istodetect anddeal with a leak from a primary system dischargingintothe Reactor Building. However, there isnoguidance to NOTenter theEOP this if cause canbe ruled out.
| |
| D. Incorrect -
| |
| EOP-5 bases doNOTspecificallycover a dropped fuel bundle, howeverthereis noguidance toNOTenter theEOPduetoadropped fuelbundle.If the droppedfuelbundle occurred inthe Spent FuelPool andcaused thishigh radiation while level theplant was operating atpower, EOP-5 entry would berequired.AOP-44 wouldthen beexecuted in parallel with EOP-5.
| |
| Technical Reference(s): EOP-5, MIT-301.11F, EP-1 Proposed references tobeprovided toapplicants during examination: None Learning Objective: MIT-301.11F 1.04 Question Source: Bank 14-1 NRC#80 Question History: 14-1 NRC#80 Question Cognitive Level:Comprehension orAnalysis 10CFRPart 55Content:55.43(5)
| |
| Comments:
| |
| | |
| ES-401 Written Examination Question Worksheet FormES-401-5 Examination OutlineCross-
| |
| | |
| ==Reference:==
| |
| Level SRO Tier # 3 Group #
| |
| K/A# 2.4.30 Importance Rating 4.1 Knowledge ofevents related tosystem operation/status that mustbereported tointernal organizations orexternal agencies, suchastheState, theNRC,orthetransmission system operator.
| |
| Proposed Question: #100 Theplant isoperatingat100%power with thefollowing:
| |
| a A plant transient withmultiplesystem malfunctions occurs.
| |
| a Plant conditionsresultintheShift Manager declaring a Site Area Emergency (SAE).
| |
| Which oneofthe followingdescribes the time requirement for notifyingthe County, State, and NRC,inaccordance with EP-CE-114-100, Offsite Notifications?
| |
| TheCounty andState mustbenotified within(1)ofthe SAE declaration.
| |
| TheNRCmustbenotified immediately after notification ofthe County and State, notto exceed .(2) .
| |
| from theSAEdeclaration.
| |
| (1) (2)
| |
| A. 15minutes 1hour B. 15minutes 30minutes C. 30minutes 1 hour D. 30minutes 30minutes
| |
| | |
| Proposed Answer: A Explanation: TheCounty andState mustbenotified through transmittalofthePart1 notification within 15minutes oftheemergency declaration.TheNRCmustbenotified through transmittal of the NRCEvent NotificationWorksheet immediately after oftheCounty notification andState and not laterthan 1hour afterthe emergency declaration.
| |
| B. Incorrect -
| |
| The NRC notification is required withina maximum of1hour,not30minutes, such the a sif two notifications each were g iven a 15 minute maximum.
| |
| C.Incorrect -
| |
| TheCounty and State notificationsarerequired within 15minutesofdeclaration, not 30minutes. 30minutes isthemaximumtime from whenconditions requiring declaration arepresent intheControl Room (15minutes max for d eclaration+ 15minutesmax for notification).
| |
| D. Incorrect -
| |
| TheCounty andState notifications are required within 15minutesofdeclaration, not 30minutes. 30minutes isthe maximum time from whenconditions requiring declaration are present intheControl Room(15 minutes maxfor declaration + 15minutesmaxfor notification). TheNRCnotification isrequired withinamaximum of1hour,not30minutes, such asif the twonotifications each weregiven a 15minute maximum.
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| Technical Reference(s): EP-CE-114-100 Proposed references tobeprovided toapplicants during examination: None Learning Objective: EP-12.5.4.1 EO4.01 Question Source: Bank 14-2 NRC#98 Question History: 14-2 NRC#98 Question Cognitive Level:Memory orFundamental Knowledge 10CFRPart 55Content:55.43(1)
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| Comments:}}
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