Text

Draft - RO & SRO Written Exam (Folder 2)
	ML050250141
Person / Time
Site:	Oyster Creek
Issue date:	01/24/2005
From:	Hackenberg J; AmerGen Energy Co
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	2130-04-20244
	Download: ML050250141 (134)
	v • d • e

_ _ - ~-

NUREG 1021 October 26, 2004 2130-04-20244 R. J. Conte, Chief, Operational Safety Branch U. S. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, PA 19406-1415 Oyster Creek Generating Station Docket No. 50-219

Subject:

Submittal of Initial Operator License Examination In accordance with NUREG 1021, Revision 9, Operating Licensing Examination Standards for Power Reactors, Oyster Creek Generating Station is submitting the initial operator license written examination, both RO and SRO, for review and approval. This is in support of the NRC initial license written examination retake scheduled for the week of December 6,2004.

In accordance with NUREG 1021, Revision 9, Section ES-201, we request that these materials be withheld from public disclosure until after the examinations are complete.

If any further information or assistance is needed, please contact Mr. Greg Young at 609-971-4196.

Herbert G. Tritt, II Facility Representative/OperationsSupport Manager Oyster Creek Generating Station HGT/DIF

Enclosures:

(Delivered only to John Caruso, Chief Examiner, NRC Region 1)

One copy of the Oyster Creek written exam ES-201-3, Examination Security Agreement ES-401-6, Written Exam Quality Checklist ES-401-4, Record of Rejected WAS cc: R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No. 04015

W Knowledge and Ability Reference Information RO SRO 29500 1 Partial or Complete Loss of AK3.02 Importance 3.7 3.8 Forced Core Flow Circulation Rating responses as they apply to PARTIAL OR -

COMPLETE LOSS OF FORCED CORE I Reactor power response FLOW CIRCULATION: I Given the following:

The reactor is at 100% power and stable Five reactor recirc pumps are operating The C reactor recirc MG Drive Motor breaker trips on overcurrent Reactor power stabilizes at 75% following the drive motor breaker trip Which of the following is the correct plant response as the operator carries out the immediate operator actions of ABN-2, Recirculation Pump Trip? Assume no change to the Recirc Master Flow Controller setpoint during this transient.

Power will.. .

v rise during the first two minutes of operator action due to the pump discharge valve A.

closing drop during the first two minutes of operator action due to the pump discharge valve 6.

closina C. remain at 75% throughout the transient due to the Recirc Master Flow Controller setpoint rise during the first two minutes of operator action due to the pump discharge valve Dm closing, thE return to 75%

I I

REFERENCE@ I ABN-2 I [ref #21 1 [ref #3]

A is correct, as the discharge valve shuts, less flow is bypassed from the core, therefore more core flow after the discharge valve is fully shut.

B is incorrect, as the sequence is backwards.

Explanation: C is incorrect as core flow will change during execution of ABN-2. This would be indicative of a discharge valve that failed to close.

D is incorrect, as final power will be greater due to less bypass flow through References to be None [ref prv #2]

provided during exam:

Learning 10450 0bjective

Question Source Bank I Modified Bank I I New [XI L Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I (b) (5) I 55.43 I

Knowledge and Ability Reference Information RO SRO 295003 Partial or Complete Loss of AC AA1.03 Importance 4.4 Power Rating Ability to operate and/or monitor the following as Systems necessary to safe plant they apply to Partial or Complete Loss of AC shutdown.

Power:

0 Buses 1C and 1 D are being supplied by their respective EDGs RPV pressure is being maintained at 935 psig with Isolation Condensers Oyster Creek has been informed that offsite power will be restored no sooner than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months A. 1.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months B. 2.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C. 19 hours2.199074e-4 days 0.00528 hours 3.141534e-5 weeks 7.2295e-6 months D. 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months I ABN-36 I [ref #21 I [ref #31 Maximum allowable cooldown rate during loss of AC power is 10 deg. F/hr.

Starting temperature 8 935 psig is 538 deg. F SDC interlocks clear @ 350 deg. F Required cooldown of 188 deg. F to clear SDC interlocks.

Explanation:

References to be Steam tables [ref prv #2]

Learning 10450 0bjective Question Source Bank I Modified Bank I I New [XI Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 295005 , Main Turbine Generator Trip AKl.01 Importance 4.0 Rating Knowledge of the operational implications of the following concepts as they apply to Main Turbine Pressure effects on reactor power Generator Trip:

Given the following:

A plant startup is in progress Reactor pressure is 300 psig and rising slowly Turbine shell warming is in progress 5 minutes later the main turbine trips Based on the above conditions, reactor power will.. .

A. I rise due to loss of feedwater heatina.

6. 1 rise due to a rise in reactor Dressure.

C. 1 lower due to a droD in reactor messure.

D. I lower due to an automatic scram.

ANSWER: IC REFERENCE(S):

315.1, step 3.3.1 3.3 A. is incorrect, as feedwater heating is not in service below -30% power.

B. is incorrect, steam flow is cutoff, but BPV will open, lowering pressure.

Explanation:

C. is correct, as all Bypass Valves will open following the trip.

D. is incorrect, as the turbine trip scram is bypassed below 30% (40% by Tech Specs.)

I NOTE: -Thisevent occurred during 1R18 startup and is an LER References to be provided I None

~

Learning 1196,1200 Objective Question Source Bank I Modified Bank I 1 New [XI Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (5) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 295006 Scram AK1.03 Importance 3.7 4.0 Rating Knowledge of the operational implications of the Reactivity control following concepts as they apply to Scram:

The reactor scrammed from 100% power All red scram lights on 4F are LIT The B CRD pump is out of service for motor winding checks Three control rods indicate 4 8 on the full core display All other control rods indicate GREEN-GREEN on the full core display Which of the following actions will provide the MAXIMUM dP for successful rod insertion?

A. Reset the scram and then manually re-scram the reactor.

B. Place the mode switch to REFUEL and manually drive the rods C. Close the CRD cooling water pressure control valve and manually drive the rods D. Reset the scram and individually scram the rods from the Rod Scram Test Panel ANSWER: ID REFER ENCE(S) : SP-21 I [ref #2] I [ref #3]

scram discharge volume will not be vented and charging header pressure will be lower.

Explanation:

B is incorrect, as the drive pressure will be significantly below scram pressure for those three rods.

C is incorrect, as the cooling water pressure will be significantly below scram pressure for those three rods.

D is correct, as this develops maximum dP for the individual rod scrams.

References to be provided None [ref prv #2]

during exam:

Learning 10450 Objective Question Source Bank I Modified Bank I I New [XI Question Cognitive Memory or Fundamental Comprehensionor [XI Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (5) 55.43 Content:

Question # 16 Examination Out Iine Cross-reference Level I RO I Tier # I 1 I GrouD# I 1 Knowledge and Ability Reference Information RO SRO 295006 Scram AA2.01 Importance 4.5 4.6 Rating Ability to determine and interpret the following as Reactor power response they apply to Scram:

Question:

The reactor is operating at 100% power, when a loss of offsite power occurs.

Reactor Dower will..

A. I initially rise, then immediately drop due to a scram when the turbine stop valves close.

B. I initially rise, then immediately drop due to a scram when the acceleration relay actuates.

C. I immediately drop due to a scram when the turbine stop valves close.

D. I immediately drop due to a scram when the acceleration relay actuates.

REFERENCE(S):

UFSAR, section

[ref #21 [ref #3]

15.2.2.2 A. is incorrect because the stop valve closure happens after the Explanation:

acceleration relay actuates.

References to be provided None [ref prv #2]

during exam:

Learning 10450,01086,10453 Objective Question Source Bank I Modified Bank I I New [XI Question Cognitive Memory or Fundamental [XI Comprehensionor Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (5) 55.43 Content:

Question # 17 I Examination Outline Cross-reference Level I RO ITier# 11 . IGrouD# 1 1 Knowledge and Ability Reference Information RO SRO 295016 Control Room Abandonment AA2.02 Importance 4.2 4.3 Rating Ability to determine and/or interpret the following as they apply

. . . to CONTROL ROOM Reactor water level ABANDONMENT:

Question:

Given the following:

A Control Room fire necessitated a Control Room Evacuation All necessary actions IAW ABN-30, Control Room Evacuation were performed prior to leaving the Control Room The Plant Process Computer has failed, and the backup Plant Process Computer is not available Based on the above conditions, RPV water level indication is available at the Remote Shutdown Panel AND at.. .

C is incorrect, as it does not address the triple low Barton on RK01/2 and RK03/5 has no RPV water level instrumentation on it..

Knowledge and Ability Reference Information RO SRO 29501 8 Partial or Complete Loss of AK1.O1 Importance 3.5 3.6 Component Cooling Water. Rating Knowledge of the operational implications of the Effects on component/system following concepts as they apply to partial or operations complete loss of component cooling water:

A. Isolate the RWCU system to reduce heat loads.

B. Start the standby RBCCW pump.

C. Commence a Dlant shutdown IAW Procedure 203.

ANSWER: IC REFERENCEW ABN-I 9 I [ref #2] I [ref #3]

A. is incorrect, would be correct for reducedcooling capability, not for a leak.

B. is incorrect, would be correct for a pump trip, not for a leak.

Explanation:

C. is the correct answer, and is dictated for a leak where surge tank level can be maintained, D. is incorrect, would be correct for a major leak where surge tank level cannot be References to be provided NONE [ref prv #2]

during exam:

Learning 00061 Objective Question Source Bank I Modified Bank 1 1 New [XI Question Cognitive Memory or Fundamental Comprehension or 1x1 Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (4) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 295019 Partial or Complete Loss of G2.1.30 Importance 3.9 3.4 Instrument Air Rating The plant has experienced a total loss of Instrument Air The reactor was scrammed successfully RPV water level is 175 in. TAF and slowly rising All feedwater pumps are secured A CRD pump is operating A. Manually close Charging Header Isolation V-15-52 B. Manually close CRD Flow Control Valves NC-30 A/B C. Manually close CRD Bypass Isolation Valve V-15-30 D. Manually open RWCU Letdown Flow Control valve ND-22 ANSWER: \A REFERENCE(S): ABN-1 I [ref #2] I [ref #3]

References to be None [ref prv #2]

Learning 10450 Objective Question Source Bank I Modified Bank 1 1 New [XI Question Cognitive Memory or Fundamental Comprehensionor [XI Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 295021 Loss of Shutdown Cooling G2.4.48 Importance 3.5 3.8 Rating 0

0 The plant is shutdown Shutdown cooling is in service with " A and "B" SDC loops in service

.+)

3rd 0 "C" SDC loop is filled and vented, and has 1500 gpm RBCCW flow through 0 RPV temperature is 310 deg. F and being cooled down at 10 deg. F per 0 The temperature switch for the " A SDC inlet water temperature fails B is incorrect, but would be correct for a recirc pump suction temperature Explanation:

switch fault.

References to be None [ref prv #2]

Learning 00026 0bjective SDC

Question Source Bank I Modified Bank I I New [XI u Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledae Analvsis

Knowledge and Ability Reference Information RO SRO 295023 Refueling Accidents AA2.01 Importance 3.6 4.0 Rating Ability to determine and/or interpret the following as they apply to REFUELING Area radiation levels ACCIDENTS:

Given the following conditions:

T = 0 minutes The plant is in a refueling outage 0 Reactor Building HVAC radiation monitor reading 2 mr/hr 0 B9 and C9 radiation monitors are both reading 3 mr/hr T = 30 minutes:

B9 and C9 radiation monitors are reading 120 mr/hr SGTS has initiated and Reactor Building HVAC has tripped Based upon these conditions, which of the following has occurred?

A. 1 A fuel bundle has been dropped B. I A fuel bundle has been misplaced in fuel pool C. I Fuel Pool skimmer surge tank is overflowing ANSWER: IA REFERENCE(S): 205.0 References to be None I I I

~

Question Source Bank Modified Bank New X Question Cognitive Memory or Fundamental Comprehension or X Level: Knowledge Analysis c

Question # 12 I Examination Outline Cross-reference Level I RO I Tier # I 1 I Group# 1 I Knowledge and Ability Reference Information RO SRO 295024 I High

- D w e l l Pressure I EA1.06 I Importance 3.7 3.7 1 Rating Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE: Emergency Generators Question:

Given the following:

The plant is operating at 100% power and stable High Drywell Pressure sensor RV-46B fails high All other Drywell Pressure sensors indicate 1.2 psig What effect does this have on the plant?

A. 1 NZOl B and NZ03B start. both EDGs idle start - f W B. I NZOl B and NZ03B start, ONLY #2 EDG idle starts C. I NZOlA&B start. NZ03A&B start, both EDGs idle start D. I NZOlA&B start, NZ03A&B start, ONLY #2 EDG idle starts

-ANSWER:

- - - - -- -. IC- I REFERENCE(S): I 341, B-l-e I [ref #2] I [ref #3]

A is incorrect as both core spray systems start B is incorrect as both core spray systems and both EDGs start.

Explanation: C is the correct answer, both core spray systems and EDG start logic is cross connected D is incorrect as both EDGs start.

References to be provided I None I [ref prv #21 Learning 00788 0bjective Question Source I Bank I I Modified Bank I I New I [Xl Question Cognitive Level:

10 CFR Part 55 1 Memory or Fundamental [XI Knowledge I I Comprehension or Analysis 55.41 (b) (7) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 295025 High Reactor Pressure EA1.07 Importance 4.1 4.1 Rating Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE:

ARI/RPT/ATWS (Plant Specific)

Question:

Given the following:

The plant is at 45% power and stable MSlVs inadvertently close All control rods remain at their pre-transient positions RPV pressure peaks at 1066 psig, then drops to 1040 psig within 5 seconds An operator is controlling pressure between 800 to 1000 psig with ICs & EMRVs 0 NO other operator actions are taken Based on the above conditions, reactor power will drop due to a .. .

partial loss of recirculation flow, and will ultimately reach the source range because of A.

ARI actuation complete loss of recirculation flow, and will ultimately reach the source range because of B.

ARI actuation

partial loss of recirculation flow, and will remain at that lowered power level, ultimately requiring an Emergency Depressurization due to exceeding the HCTL complete loss of recirculation flow, and will remain at that lowered power level, ultimately D.

requiring an Emergency Depressurization due to exceeding the HCTL ANSWER: IC REFERENCE(S): E-1 -a I [ref #2] I [ref #3]

References to be provided None [ref prv #2]

during exam:

Question Source Bank I Modified Bank I I New [XI Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (6) 55.43 Content:

W Knowledge and Ability Reference Information RO SRO 295026 Suppression Pool High Water G 2.1.25 Importance 2.8 Temperature Rating An Emergency Depressurization has been performed and all 5 EMRVs are open

RPV level is being maintained 100 to 175 in. TAF Torus pressure is being maintained between 4 and 12 psig 0 Core Spray pumps NZOlA and NZO16 are operating at 4,000 gpm each Torus water level is 150 inches and stable Containment Spray pump 51A is running in Torus Cooling mode at 4,500 gpm 0 Containment Spray pump 51C is running in Drywell Spray mode at 4,500 gpm What is the HIGHEST Torus temperature that is allowed without exceeding any Core Spray I imits?

v A. I 190dea. F B. I 193 dea. F C. I 200dea. F D. I 202 dea. F I

REFERENCE(S I SP4 1 [ref #2] 1 [ref #3]

For the conditions stated, CS static head adjustment is 2.1 psig.

For 12 psig - I static head adjustment.

For 4 psig - Gstatic head adjustment.

Use 4 psig and static head of 2.1 and NZOl C NOT running curve to Explanation: determine 193 deg. F is the highest temp. Therefore:

A is incorrect as it is using the NZOl C curve.

B is correct.

C is incorrect as it is using 12 psig and the NZO1C curve References to Ld SP-4 [ref prv #2]

Learning 03023 Objective

Question Source Bank I Modified Bank I I New [XI

..--,, Question Cognitive

- Memory or Fundamental I I Comprehension or [XI Level: I Knowledge I Analysis

Knowledge and Ability Reference Information RO SRO 295028 High Drywell Temperature EA2.03 Importance 3.7 Rating Ability to determine and/or interpret the Following as they apply to HIGH DRYWELL Reactor water level TEMPERATURE:

A small steam line break has occurred in the drywell RPV pressure is 500 psig and stable Bulk drywell temperature is 255 deg. F and stable AYarway reference leg temperature is 495 deg. F B Yarway reference leg temperature is 500 deg. F NR & WR GEMAC reference leg temperatures are 450 deg. F Yarway instruments read 90 in. TAF and stable NR GEMAC instruments read 92 in. TAF and stable WR GEMAC instrument reads 170 in. TAF and stable Based upon the above, RPV water level.. .

A. 1 is 90 in. TAF B. I is 92 in. TAF ~ ~~ ~~~~~~~~~

C. is 170 in. TAF D. cannot be determined REFERENCE(S): 1 SP-28 1 [ref #2] I [ref #3]

I All instruments are below RPV saturation pressure, therefore:

A is incorrect as it is below minimum usable indicating level Explanation: B is incorrect as it is below minimum usable indicating level C is correct. Minimum usable level is -1 55 in.

D is incorrect, as the WR instrument is usable References to be SP-28 [ref prv #2]

Learning 10445 Objective Question Source Bank 1 ModNed Bank I I New [XI Question Cognitive Memory or Fundamental [ Comprehension or Level: Knowledge L Analysis

Knowledge and Ability Reference Information RO SRO 295030 Low Suppression Pool Water EK2.08 Importance 3.5 3.8 Level Rating Knowledge of the interrelations between LOW SUPPRESSION POOL WATER LEVEL and EMRV discharge submergence the followina:

Question:

Given the following:

The plant is operating at 100% and stable The TORUS LEVEL HVLO alarm annunciates The STA informs you that torus water level is low, and dropping at 2 inches per minute Assuming the time starts low level alarm is received and assuming a constant rate of torus level drop, two questions.

1. What is

2. What is thtstmseeh,yae n?

A.

B.

I Approximately 16 to 17 minutes, due to loss of suppression capability when EMRVs are oDen.

Approximately 16 to 17 minutes, due to loss of suppression capability for a LOCA fV.

? Approximately 26 to 27 minutes, due to loss of suppression capability when EMRVs are open.

D. Approximately 26 to 27 minutes, due to loss of suppression capability for a LOCA.

RPV Control - No REFERENCE(S): EOP Users Guide AS At 2 in/min drop, it has to go from 1 4 3 to 9 0 , or -53/2 or 26.5 minutes.

At 110 inches, torus downcomers are uncovered. At 90 inches, EMRV Y quenchers are uncovered.

Explanation: A is incorrect because the EMRVs are still covered.

B is correct for basis for torus downcomers uncovered, but not for EMRVs.

C is correct 1 D is incorrect due to wrong basis applied.

References to be I None Learning 00369 Objective

Question Source Bank I Modified Bank 1 1 New [XI Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledae Analvsis

W Question # I 17 Knowledge and Ability Reference Information RO SRO 295031 Reactor Low Water Level EK3.05 Importance 4.2 4.3 Rating Knowledge of the reasons for the following responses as they apply to REACTOR LOW Emergency depressurization WATER LEVEL:

0 The Steam Cooling EOP was entered when RPV level reached 0 in. TAF RPV pressure is being maintained between 800 and 1000 psig with ICs 0 The B CRD pump has been started and is injecting to the RPV NO other injection systems are available RPV water level is -35 in. TAF and steady Based upon the above information, which of the following is correct and why?

W I

A is incorrect, because level must be above -20 in to ensure clad does not exceed 1500 deg. F.

B is incorrect, because the 4 2 in level corresponds to less than 1800 deg.

F with NO injection and no subcooling. By having CRD injection, this Explanation:

invalidates all steam cooling assumptions.

C is incorrect, because level must be above -20 in to ensure clad does not exceed 1500 deg. F.

D is correct References to I : I Steam Cooling EOP Learning 10450 0 bjective

Question Source Bank I Modified Bank I 1 New X Question Cognitive

- Memory or Fundamental I I Comprehension or X Level: I Knowledge I Analysis

~~-

295037 SCRAM condition present anc EK2.10 Importance 3.8 Reactor Power above APRM Rating Downscale or Unknown Reactor pressure The plant is at 100% power when the following occurs:

The Main Turbine trips A hydraulic ATWS occurs Between 2 and 3 turbine bypass valves are controlling RPV pressure at 935 psig Torus temperature is 76 deg. F and steady All reactor recirculation pumps are tripped There are NO power oscillations RPV water level is being maintained between -20 and 30 in. TAF with Feedwater and Condensate e Control rods are being manually inserted IAW SP-21 Based upon these conditions, wh a plant cooldown be commenced?

A. I When liquid poison tank is ad 150 kallons B. When power reaches IRM rar)se/4, and is continuing to lower C. Immediately, since power is within the capacity of the turbine bypass valves ANSWER: IB REFERENCE(S): EOPs I [ref #2] I [ref #3]

A is incorrect because there is no need to inject boron under these conditions.

Explanation: B is correct, the reactor is shutdown C is in correct, because the reactor is still at power.

D is incorrect, because power is still in the power range at 2%

References to be EOP flowcharts [ref prv #2]

provided during exam:

Learning 10450,02257 0bjective

Question Source Bank I Modified Bank I I New [XI v Question Cognitive

- Memory or Fundamental I I Comprehensionor [XI Level: I Knowledge I Analysis

Knowledge and Ability Reference Information RO SRO 295038 High Off Site Release Rate EK2.07 Importance 3.5 Rating Knowledge of the interrelations between HIGH Room ventilation OFF-SITE RELEASE RATE and the following:

Question:

Given the following conditions:

The plant is operating at 100% power and steady D Annunciator 1OF-l-d, STACK EFFLUENT HI-HI alarms Stack RAGEMS Channel 1 & 2 are reading above their HI-HI alarm setpoint Which of the following correctly describes the Control Room HVAC System lineup for these conditions?

A. I Normal Mode B. I PuraeMode C. I Partial Recirculation Mode REFERENCE(S): I '30.1.1 1 3 3 1 . 1 I [ref #21 I I

[ref #3]

A is incorrect, as normal mode will not create a positive pressure in the control room.

B is incorrect, as purge mode is only used to Explanation: odors from the atmosphere.

C is correct in accordance with actions D is incorrect as full recirc mode prevents control room.

References to be None [ref prv #2]

Learning 02324 Objective Question Source Bank 1 Modified Bank I I New [XI Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledge Analysis c

Knowledge and Ability Reference Information RO SRO 600000 Plant Fire On Site AA1.09 Importance 2.5 Rating Ability to operate and/or monitor the following Plant fire zone panel, including detector as they apply to PLANT FIRE ON SITE: location Given the following:

The plant is operating at 100% power 0 The B Control HVAC system is operating in Normal mode 0 A fire starts in the Control Room due to a relay burning up 0 Significant amounts of smoke and combustion products are present from the fire 0 The fire CANNOT be extinguished with portable extinguishers The following detectors have activated:

0 2 detectors in Zone 1 for System A 3 detectors in Zone 2 for System B 0 1 detector in Zone 1 for System C 2 detectors in Zone 2 for System C Which of the following Control Room Halon system(s) will actuate?

D. System A, B and C E. System A and B ONLY F. System B and C ONLY D. System C ONLY A. I System A, B and C B. I System A and B ONLY C. I System B and C ONLY ANSWER: ID R EFERENCE(S) : ABN-29 I [ref #2] I [ref #3]

A is incorrect, two detectors from opposing zones must actuate to cause HALON actuation.

B is incorrect, two detectors from opposing zones must actuate to cause Explanation: HALON actuation.

C is incorrect, since two detectors from opposing zones must activate to cause auto initiation of HALON.

D is correct, two detectors from opposing zones have actuated References to be None [ref prv #2]

Learning 10445,10450 Objective 1 I I W'

Question Source Bank Modified Bank New [XI Question Cognitive Memory or Fundamental I I Comprehension or [XI Level: ] Knowledge I Analysis

Knowledge and Ability Reference Information RO SRO 295008 High Reactor Water Level AA2.02 Importance 3.4 3.4 Rating Ability to determine and/or interpret the following as they apply to HIGH REACTOR Steam flow/feed flow mismatch WATER LEVEL:

The plant is at 100% power RPV water level is being maintained at 160 in. TAF in AUTO Indicated steam flow is 7.20 E6 Ibm/hr Indicated feed flow is 7.1 6 E6 Ibm/hr B EMRV fails open 0 NO operator actions are taken Once the plant stabilizes, RPV water level will be (1) AND the steam flow/feed flow mismatch will be (2) pre-transient conditions.

(1) above 160 in. TAF A-(2) less than (1) below 160 in. TAF B- (2) less than (1) above160 in. TAF

c. (2) greater than (1) below 160 in. TAF Dm (2) gre: er than I

I ABN-40 I EMRVs tap off upstream (vessel side) of the steam flow restrictors, such that the steam flow through an open EMRV will not be indicated. When this happens, the FWLC system will see a reduced steam flow, and the feed-forward component will cause FRVs to close. As level drops below the setpoint, the level error will eventually overcome the steam flow/feed flow Explanation:

mismatch, and will control at a lower level. Therefore:

A is incorrect as level will be lower and mismatch will be higher B is incorrect as mismatch will be greater C is incorrect as level will be lower

?eferencesto be None wovided during exam:

-earning 10450 3bjective

Question Source Bank I Modified Bank I I New X v Question Cognitive

- Memory or Fundamental I I Comprehensionor X Level: I Knowledge I Analysis

Knowledge and Ability Reference Information RO SRO 295007 High Reactor Pressure G2.1.23 Importance 3.9 4.0 Rating 0 MSlVs close on high Trunnion Room temperature 0 All rods remain at their pre-transient positions 0 RPV pressure is 1215 psig and steady Drywell pressure is 17 psig and rising All other systems operated as expected Reactor pressure will be reduced by.. .

A placing BOTH ICs in service, IAW SP-11 B terminating and preventing injection, IAW SP-17 C reopening MSIVs, IAW RPV Control -with ATWS D manually opening ALL EMRVs, IAW Emergency Depressurization REFERENCE(S): I 1

~ ~ ~ t r oEOP l Users Guide 1 [ref #3]

Explanation:

References to be EOPs without entry conditions provided during exam:

Learning 02257 0 biective Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis

Question # I 2 3 Examination Outline Cross-reference Knowledge and Ability Reference Information RO SRO 295010 I High Drywell Pressure I AK1.03 I Importance 3.2 3.4 Knowledge of the operational implications of the following concepts as they apply to HIGH Temperature increases D R W E L L PRESSURE:

~~~~

Question:

Given the following:

A high drywell pressure condition is in progress 0 Drywell pressure is 1.8 psig and rising slowly Bulk drywell F and rising slowly Which of the following is NOT strategy for lowering Drywell pressure*

v- I A. I Reduce RBCCW loads.

B. I Start all d w e l l coolinn fans.

C. I Start the second RBCCW wmD.

ANSWER: ID REFERENCE(S): RAP C-3-f I C-8-h B is addressed in C-3-f Explanation:

C is addressed in C-3-f References to be None Learning 00446 Obiective I I I

~ _ _ _

Question Source Bank Modified Bank New [XI Question Cognitive Memory or Fundamental I [XI I Comprehension or

Knowledge and Ability Reference Information RO SRO 295013 High Suppression Pool AK2.01 Importance 3.6 3.7 Temperature Rating Knowledge of the interrelations between HIGH SUPPRESSION POOL TEMPERATURE and Suppression pool cooling the following:

0 A plant startup following a refueling outage is in progress RPV pressure is 1020 psig Reactor power is 4%

EMRV testing is in progress Torus cooling is in operation Average torus temperature is rising (1) 105 A-(2) 110 (1) 110 Bm (2) 120

c. (2)(1) 95 110 Dm (1) 105 (2) 120 Tech REFERENCE(S): Specs 3.5.A.1 .c A is correct.

B is incorrect. Scram is at 110 and RPV depressurization at 120.

Explanation: C is incorrect. Normal operating limit is 95, and scram is 110.

D is incorrect. EMRV testing can go to 105, but RPV depressurization is 120.

References to be None Learning 10450 Objective

Question Source Bank I Modified Bank I I New [XI l./Question

, Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I (b) (3) I 55.43 I

Knowledge and Ability Reference Information RO SRO 295022 Loss of CRD Pumps AK3.01 Importance 3.7 3.9 Rating Knowledge of the reasons for the following responses as they apply to LOSS OF CRD Reactor Scram Question:

Given the following:

A plant startup is in progress RPV pressure is 800 psig 0 The A CRD pump trips on overload and CANNOT be restarted 0 The B CRD pump will not start A scram is required (1) and rod scram times will be (2) allowable limits (1) immediately A.

(2) within (1) immediately B-(2) greater than (1) when the second accumulator alarms cm (2) within r\ I (1) when the second accumulator alarms Y.

I (2) greater than ANSWER: IA H-7-c REFERENCE(S):

RAP A is correct B is incorrect, as the accumulators will ensure all rods will scram within TS times.

C is incorrect, waiting for the second accumulator is correct when RPV Explanation:

pressure is above 850 psig. With accumulator alarms in, scam times may not be within allowable limits D is incorrect, waiting for the second accumulator is correct when RPV pressure is above 850 psig.

References to Lz I None provided during exam:

Learning I 10450

Question Source Bank I Modified Bank I I New [XI u Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledae Analvsis

Knowledge and Ability Reference Information RO SRO 295029 High Suppression Pool Water EK3.01 Importance 3.5 Level Rating Knowledge of the reasons for the following responses as they apply to HIGH Emergency depressurization SUPPRESSION POOL WATER LEVEL:

0 The plant has experienced a small LOCA 0 The reactor has been scrammed 0 Drywell pressure is being maintained between 4 and 12 psig with drywell sprays RPV pressure is steady at 800 psig 0 RPV level is being maintained between 138 and 175 in. with Condensate/Feedwater and CRD 0 Torus level is 180 inches and rising at approximately 1 in. every 3 minutes 0 The US has ordered Emergency Depressurization What is the basis for this decision?

A. To prevent exceeding the PCPL if the LOCA were to progress to a DBA LOCA.

B. To prevent exceeding allowable stresses on the EMRV Y quenchers and supports.

C. To lower pressure as necessarv to allow the low pressure iniection systems to inject.

I D. To prevent possible torus structural damage due to the elevated water level.

ANSWER: IB EOP REFERENCE(S): TLL curve bases A is incorrect. If torus level cannot be maintained in the PSP and a vessel breach by core materials were to occur, the PCPL could be exceeded, but not by a DBA LOCA.

B is the correct answer, based upon the definition of the Torus Load Limit Explanation:

curve.

C is incorrect, as we are not in the Level Restoration leg of RPV control.

D is incorrect. Structural damage will occur only if torus level is significantly References to be EOPs without entry conditions Learning 03000 0bjective

Question Source Bank I Modified Bank I I New [XI J Question Cognitive Memory or Fundamental [XI Comprehensionor Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 295009 Low Reactor Water Level AA1.02 Importance 4.0 4.0 Rating Ability to operate and/or monitor the following Reactor water level control as they apply to Low Reactor Water Level:

Question:

Given the following:

Plant is at power 0 Feed flow is 5.5 E6 I b d h r 0 3 feed pumps operating 0 Reactor level control is in AUTO 0 Master feedwater level setpoint is 160 in.

0 Bfeed pump trips With NO operator action, feed flow will be.. .

A. I 5.5 E6 Ibm/hr B. I 5.34 E6 Ibm/hr C. 1 4.8 E6 Ibm/hr

Knowledge and Ability Reference Information RO SRO 205000 Shutdown Cooling K4.01 Importance 3.7 Rating Knowledge of the Shutdown Cooling system design features(s) and/or interlocks which provide High temperature isolation for the following:

Given the following:

0 Shutdown cooling is in operation with A Shutdown Cooling (SDC) Pump running 0 E Recirculation Loop is in service; all other loops are idle The C recirc loop temperature instrument fails upscale SDC system will isolate on low suction pressure AND running SDC pumps will trip on A.

high temperature Running SDC pumps will trip on low suction pressure AND SDC system will isolate on 6.

low suction pressure SDC system will isolate on high temperature AND running SDC pumps will trip on

c. isolation valve closure Running SDC pumps will trip on high temperature AND SDC system will isolate on high D.

temperature ANSWER: IC REFERENCES): Proc. 305, C-2-d I [ref #2] I [ref #3]

valve closure.

B is incorrect, inlet and outlet valves will close on high temp, NOT low Explanation: pressure.

C is the correct answer, inlet and outlet valves on high temp, pumps isolation valve closure.

References to be provided None [ref prv #2]

durina exam:

Learning 00401 Objective Question Source Bank I Modified Bank I I New [XI Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (7) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 207000 Isolation Condenser K1.03 Importance 3.7 Rating Knowledge of the physical connections and/or cause-effect relationships between Reactor water level ISOLATION CONDENSER and the following:

A. 160 in., to prevent water hammer of the piping.

B. 160 in., to prevent automatic isolation.

C. 180 in., to prevent water hammer of the piping.

D. 180 in., to prevent automatic isolation.

REFERENCE6 I EOPs 1 Support Procedure 11 I A is incorrect, as this is the basis for not initiating ICs above 160 inches, not for isolating them.

6 is incorrect, as the level pertains to initiation, and the high flow isolation Explanation: deals with recirc pumps N E running if ICs are initiated.

C is correct D is incorrect, as the isolation on high flow precaution is to ensure recirc pumps NE are ..

secured prior to initiation.

Referencesto be provided during exam:

Learning 02338 I None 0bjective QuestionSource Bank I Modified Bank I I New [XI QuestionCognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 209001 Low Pressure Core Spray K2.03 Importance 2.9 3.1 System Rating Knowledge of electrical power supplies to the logic following:

Question:

A- (1) A (2) NZOl B and NZOl C B- (1) B (2) NZOl B and NZOl C

c. (1) ANZOlA and NZOl B (2)

Dm (1) B (2) NZOlA and NZOl B ANSWER: IC REFERENCE(S): RAP 9XF-3-d I RAP B-7-e on a false high steamkondensate flow signal due to loss of power to the isolation logic. However, core spray initiation logic is provided from both DC-D and DC-F. Core spray system I pumps (NZOlA/C) initiation logic is normally from DC-D with a redundant logic circuit from DC-F. Core spray system I I pumps (NZOI B/D) initiation logic is normally from DC-F with a Explanation: redundant logic circuit from DC-D. Therefore, system I and II pump initiation logic will be powered from DC-F, and the primary main pumps will start (A and B).

A is incorrect, as the backup main pump in system I (NZO1C) will not start.

B is incorrect, as the wrong IC isolation is given, and NZOI C will not start.

C is correct References to be None Learning 02030,00302 Obiective

I I 1

~~~~ ~

Question Source ~ Bank Modified Bank New X L Question Cognitive Memory or Fundamental 1 I Comprehension or X Level: I Knowledge I Analysis

Knowledge and Ability Reference Information RO SRO 21 1000 Standby Liquid Control System K6.03 Importance 3.2 3.3 Ratina Knowledge of the effect that a loss or malfunction of the following will have on the A.C Power STANDBY LIQUID CONTROL SYSTEM:

Question:

Which of the following 460V MCCs MUST have power in order to inject with SLC System l ?

A. 1A21 B. 1A21A C. 1A22 D. 1A23 A. I 1A21 B. I l A 2 1 A C. 1 1A22 D. 1 1A23 I

REFERENCE(S I ABN-45, att. 5 A is correct, as the SLC pump 1A and it's squib are powered from 1A21, and SLC pump 1B and it's squib are powered from 1 B21.

B is incorrect, as 1A21A and 1821A power Recirc Pump and Core Spray Explanation: valves ONLY.

C is incorrect, as 1A22 and 1B22 power Old Radwaste equipment ONLY.

D is incorrect, as 1A23 and 1823 power Reactor Building and Office Building fans ONLY.

References to I ! I None Learning 10436 0bjective Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 2 12000 Reactor Protection System A3.06 Importance 4.2 4.2 Rating Ability to monitor automatic operation of the Main turbine trip: Plant-Specific REACTOR PROTECTION SYSTEM including:

Question:

The plant was operating at 40% power when the MOISTURE SEPARATOR HI-HI alarm is received and remains in for 15 seconds.

Based upon this, the reactor will (1) , and the turbine valve response will be (2)

(1) SCRAM (2) Turbine Control Valves -

Intercept Valves A.

- Reheat Stop Valves trypass valves

~ -QPEN 1

A11Tipenlhitially; throttle c l o s to

-4 control reactor fl) AM pressure (2) Turbine Control Valves B.

(1)

(2)

Intercept Valves Reheat Stop Valves Bypass Valves SCRAM Turbine Control Valves c;: O P E 4

- _ _ - CLOSED Intercept Valves C. Reheat Stop Valves- - L S E D

/---

Eypass\Fa< - All open initially; throttle closed to f5ontrol reactor pressure __-.-,

(?tj----RI-O'-SCKAM D.

AN ___ - _- -__--

- WER: \c-c_-_ - __-. -

REI ERENCE(S):

- ABN-10 1 RAP P-1-a Explanation: B is incorrect, as the reactor will scram and the turbine will trip '

C is correct D is incorrect, as the reactor will scram, and the reheat stop valves will remain open if the turbine has not tripped NOTE: This transient happened in 2003

References to be None provided during exam:

Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis

d Knowledge and Ability Reference Information RO SRO 215003 Intermediate Range Monitor K6.06 Importance 3.2 3.4 (IRM) System Rating Knowledge of the effect that a loss or malfunction of the following will have on the APRM INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM:

0 A plant startup is in progress 0 All IRMs are in Range 10 0 The mode switch has just been taken to RUN 0 IRM 13 takes a step change to 40%

0 Before IRM 13 can be bypassed, LPRM string 12-17 fails to 0 as indicated on all four (4) LPRM channels Besides the APRM DOWNSCALE alarm, which of the following will be received?

A. I LPRM DOWNSCALE alarm ONLY.

L B. I LPRM DOWNSCALE and ROD BLOCK alarms ONLY.

C. I LPRM DOWNSCALE, IRM HI-HI, and ROD BLOCK alarms ONLY.

D. I LPRM DOWNSCALE, IRM HI-HI, ROD BLOCK alarms, and CHANNEL I half scram.

ANSWER: II REFERENCE(S RAP G-1-d I RAP G-4-f I RAP G-7-f The candidate must recognize that 40% of Range 10 will cause an IRM HI-HI alarm on IRM 13. Must also determine that LPRM string 12-17 feeds APRM channels 3 and 7 (from Attachment 403-2).This combination will cause LPRM and APRM downscale alarms, Rod Block alarm, as well as a half-scram on System I due to IRM 13 upscale/APRM 3 downscale.

Explanation:

Therefore:

A is incorrect, as it is only one of four things that occur.

B is incorrect, as it is only two of four things that occur.

References to be YAttachment403-2 LPRM and provided during - exam: APRM status information

\ sheet Learning I 10441 \

0bjective

- Question Source Question Cognitive Bank I Modified Bank Memory or Fundamental I I I New I Comprehension or X

X

Knowledge and Ability Reference Information RO SRO 215004 Source Range Monitoring System K3.02 Importance 3.4 3.4 Rating Knowledge of the effect that a loss or malfunction of the SOURCE RANGE Reactor manual control: Plant Specific MONITORING SYSTEM will have on the followina:

Question:

Given the following conditions:

Rx mode switch in "Startup" IRMs in range 1 IRMs and SRMs are full in Which of the following will produce a rod block?

A. IRM 14 indicates 3 on 125 scale B. APRM 7 indicates 1 on 150 scale.

C. SRM 24 indicates 100 cps D. SRM 21 indicates 2 E5 cps A is incorrect, would be true if not in range 1.

B is incorrect. would be true if mode switch in RUN.

Explanation:

C is incorrect, would be true if detector not full in D is correct, References to be None Learning 00731,10449 Objective Question Source Bank I Modified Bank I 1 New [XI Question Cognitive Memory or Fundamental [XI Comprehensionor Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 2 15004 I Source Range Monitoring System 1 Al.01 I Importance 3.0 3.1 I Rating Ability to predict and/or monitor changes in parameters associated with operating the SOURCE RANGE 1 Detector position MONITORING SYSTEM controls including:

Question:

During startup, when the reactor is critical, SRM detectors are initially withdrawn when (1) and SRM period will (2) as the detectors start moving I

4 (1) all SRMs are greater than 1 E5 cps A-(2) become longer (1) all SRMs are greater than 1 E5 cps B.

(2) become shorter (1) three IRMs in each RPS system read 50% on range 1

c. (2) become longer (1) three IRMs in each RPS system read 50% on range 1 D.

12) become shorter As SRM detectors are initially withdrawn, the move into a higher flux area of the core causing period to become shorter. Period will become longer/go negative only after the detectors pass beyond the hiah flux area.

A. is incorrect, detector withdrawal is dictated by IRM indication and period Explanation:

will initially go shorter References to be None provided during exam:

Learning 10444 0bjective Question Source Bank 1 Modified Bank I I New [XI Question Cognitive Memory or Fundamental Comprehensionor [XI Level: Knowledge Analysis

Question # 1 36 Examination Outline Cross-reference Level I RO I Tier # 12 I Group# I 1 I RO I I I Knowledge and Ability Reference Information SRO 2 15005 I Average Power Range Importance 3.6 3.6 Monitck'Local Power-Range Rating Monitor System Ability to predict and/or monitor changes in parameters associated with operating the AVERAGE POWER RANGE Control rod block status MONITOFVLOCAL POWER RANGE MONITOR SYSTEM controls including:

Question:

Given the following:

A plant startup is in progress The Mode Switch is in RUN Reactor Power drops, causing APRM DOWNSCALE white light to ILLUMINATE Based upon the above, Control Rods. . .

A. cannot be driven in EITHER direction.

B. can be driven in the inward direction ONLY.

C. can be driven in the outward direction ONLY.

D. can be driven in the inward AND outward directions.

ANSWER: IB REFERENCE(S:: RAP H-7-a I [see question #34]

B is correct - with APRM downscale and Mode switch not in Explanation: STARTUP/REFUEL a withdraw block is applied. A/C/D are incorrect -other possible effects but withdraw block will occur for given conditions References to be None Drovided durina exam:

Learning I 10444 Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental I I Comprehensionor X

Knowledge and Ability Reference Information RO SRO 2 15005 Average Power Range A3.07 Importance 3.8 3.8 MonitorlLocal Power Range Rating Monitor System Reactor power is 70%

Total recirc flow on panel 4F is 15.0 E4 gpm The recirc flow transmitter in the C recirc loop, which feeds the Total Recirc Flow indicator on 4F, fails to 0 (zero)

Recirc flow on panel 4F will read (1) gpm, resulting in a (2)

(1) 12.0 E4 A-(2) rod block (1) 12.0 E4 B.

(2) half-scram (1) 13.5 E4 c- (2) rod block (1) 13.5 E4 Dm 121 half-scram ANSWER: /A REFERENCE(S): RAP G-5-f Only 5 of 10 recirc flow transmitters feed the 4F total recirc flow indicator, causing indicated flow to read 80% of initial flow (15 x .8 = 12). A 10% or greater flow mismatch will cause the flow comparator rod block. Therefore:

A is correct Explanation: B is incorrect, as this does NOT result in a flow comparator half scram C is incorrect, as 13.5 E4 gpm is only a 10% drop (this would be correct if all 10 flow transmitters fed the 4F total recirc flow indicator)

D is incorrect, as 13.5 E4 is only a 10% drop, and this will NOT result in a flow comparator half scram References to be Power-to-Flow Map, 202.1 -2 Learning 00219 Objective

Question Source Bank I Modified Bank I I New X v Question Cognitive Memory or Fundamental I I Comprehension or X

Knowledge and Ability Reference Information RO SRO 218000 Automatic Depressurization K3.02 Importance 4.5 4.6 System Rating malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on I Ability to rapidly depressurize the reactor the following:

Question:

Given the following:

A small break LOCA is in progress Drywell pressure rose to 4 psig All automatic actuations occurred as designed Drywell sprays were initiated and drywell pressure is stable at 1.5 psig All control rods are fully inserted RPV water level is +20 inches and stable ADS is being bypassed IAW Level Restoration ADS Timer A bypass switch has been taken to BYPASS ADS Timer B bypass switch cannot be moved from the AUTO position due to mechanical binding NO other actions were taken A. initiate and ALL 5 EMRVs will open.

B. initiate but ONLY C and D EMRVs will open.

C. NOT initiate because it is bypassed.

D. NOT initiate because d w e l l messure is 1.5 Dsia.

ANSWER: IA I REFERENCE(S I RAP B-l-h I RAP B-2-h I RAP B-5-h Drywell pressure signal for ADS seals in, and BOTH ADS timers must be in bypass in order to prevent ADS auto initiation. Therefore:

A is correct Explanation: B is incorrect, as ADS actuation will open all EMRVs, not just the ones on the North header C is incorrect, because it takes BOTH timers in bypass to inhibit ADS.

D is incorrect, because the DW pressure signals to ADS seal in.

Referencesto I ! I None Learning 10357,00379 0biective

Question Source Bank I Modified Bank I I New X b Question Cognitive Memory or Fundamental Comprehension or X Level: Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I (b) (7) I 55.43 I

Knowledge and Ability Reference Information RO SRO 223002 Primary Containment Isolation K3.10 Importance 2.9 3.1 System/Nuclear Steam Supply Rating Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM Reactor water cleanup SUPPLY SHUT-OFF will have on the following:

_ _ ~

39 Given the following:

0 The plant is shutdown 0 RPV pressure is 700 psig 0 An 18C tech causes drywell pressure transmitter RE04A to fail upscale 0 RWCU system isolates 0 REO4A has been returned to service and drywell pressure is 1.2 psig 0 RWCU pressure is 140 psig 0 Filter bypass valve V-16-83 is OPEN Based on the above, the RWCU system SHOULD (11 and the following actions are required, in the stated sequence, to open V-16-1: (2)

(1) have isolated A. (2) Depress DW ISOLATION RESET pushbutton on 4F, and reduce RWCU pressure to approximately 80 psig (1) NOT have isolated B. (2) Reduce RWCU pressure to approximately 80 psig, and depress DW ISOLATION RESET pushbutton on 4F (1) have isolated (2) Depress DW ISOLATION RESET pushbutton on 4F, reset the redundant high C.

pressure isolation keylock in A/B Battery Room, and reduce RWCU pressure to

- approximately 80 psig (1) NOT have isolated Reduce RWCU pressure to approximately 80 psig, depress DW ISOLATION D. (2)

RESET pushbutton on 4F, and reset the redundant high pressure isolation keylock in A/B Battery Room AN WER:

- ID REI High pressure isolation setpoint for primary and redundant isolation circuits Explanation: is 130 psig. It takes two (one-out-of-two twice) high drywell pressure signals to cause an isolation. Therefore:

References to be None Learning 00252 Objective Question Source Bank I Modified Bank I 1 New X Question Cognitive Memory or Fundamental Comprehension or X Level: Knowledge Analysis

ii Knowledge and Ability Reference Information RO SRO 223002 Primary Containment Isolation A4.01 Importance 3.6 3.5 System/Nuclear Steam Supply Rating Ability to manually operate and/or monitor in Valve the control room:

Question:

Given the following:

0 A plant shutdown is in progress 0 The drywell is being purged with air 0 The Mode Switch is in RUN If power is lost to VMCC 1B2, which of the following isolation valves will close?

A. I Air SUDD~V to DW (V-28-42. -43)ONLY fl DW VenVPurae Valves (V-27-1. -2. -3. -4) ONLY C DW Sump Valves (V-22-28, -29) ONLY D. DW Equipment Drain Valves V-22-1, -2) ONLY L

ANSWER: IB Inst. pwr restoration R EFERENCE(S) : RAP 10F-4-k RAP C-4-g, ABN-48 3024.10f causes CHRRMS Channel 2 to lose power. On a loss of power, all vent valves for the drywell and torus will isolate on Torus/DW Vent & Purge HI rad isolation, C-4-g. No other valves are affected. Therefore:

Explanation: A is incorrect as the air supply valves are not affected.

B is the correct answer C is incorrect, as the sump valves are not affected D is incorrect, as the drain valves are not affected (sump isolation valve isolation on loss of PAIPP panels is a common mis-conception.)

References to L2 None Learning 00394 Objective Question Source Bank 1 Modified Bank I I New [XI Question Cognitive Memory or Fundamental Comprehensionor [XI Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 239002 ReliefEafety Valves K5.02 Importance 3.7 3.8 Rating Knowledge of the operational implications of the following concepts as they apply to Safety function of SRV operation RELIEFEAFETY VALVES:

. (1)

(2) a Turbine Trip with ATWS 1,250 (1) an MSlV Closure B.

(2) 1,250 (1) a Turbine Trip with ATWS

c. (2) 1,375 (1) an MSlV Closure I

REFERENCE(S UFSAR 5.2.2.4 Safety valves are designed to ensure peak pressure does not exceed 1,375 psig. They will not open on any pressure transient except those resulting from isolation with scram failure, failure of the EMRVs, or failure of the turbine bypass valves. Therefore:

Explanation: A is incorrect, as this is not an isolation, and the pressure is SS pressure limit of 1250 psig B is incorrect, as the pressure is the steady state pressure limit of 1250 psig C is incorrect, as this is not an isolation D is correct References to be None Learning 00515,01028 Objective Question Source Bank I Modified Bank I I New X QuestionCognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis

42 Given the following:

0 The plant is at 100% power and stable 0 The feedwater LEVEL TRANSMITTER SELECTOR switch is in AUTO 0 The A white light is LIT 0 The AUTO white light is LIT 0 The B white light is OUT 0 The C amber light is OUT 0 GEMAC A is indicating 165 inches 0 GEMAC B is indicating 162 inches 0 GEMAC C is indicating 164 inches Master FW level controller is in AUTO at 165 inches If GEMAC A fails to 140 inches, what reference level will digital feedwater use to control RPV level?

A. 140 inches B. 160 inches C. 162 inches D. 164 inches

Knowledge and Ability Reference Information RO SRO 259002 I Reactor Water Level Control I A1.O1 1 Importance 3.8 3.8 Question:

Given the following:

e The plant is at 100% power and stable e The feedwater LEVEL TRANSMITTER SELECTOR switch is in AUTO e The A white light is LIT e The AUTO white light is LIT e The B white light is OUT e The C amber light is OUT e GEMAC A is indicating 165 inches e GEMAC B is indicating 162 inches e GEMAC C is indicating 164 inches e Master FW level controller is in AUTO at 165 inches If GEMAC A fails to 1407 inches, what reference level will digital feedwater use to control RPV level?

A. 140inches B. 160 inches C. 162 inches RAP J-8-c I 418.1 A is incorrect, as this level is divergent from B and C Gemac levels, therefore it is treated as a BAD signal B is incorrect, as a failure of all level transmitters will result in a default to 160 inches Explanation:

C is correct. since AUTO is selected, this will result in B transmitter indication will be used because it is the closet to C D is incorrect. If the level selector were in AUTO and both A and B transmitters failed, C would take over.

qeferences to be wovided durina exam:

-earning 10446 I None 3bjective

Question Source Bank I Modified Bank I I New X i, Question Cognitive Memory or Fundamental Comprehension or X Level: Knowledge Analysis 10 CFR Part 55 Content: I I 55.41 (b) (7) I 55.43 I

Knowledgeand Ability Reference Information RO SRO 261000 Standby Gas Treatment System K1.08 Importance 2.8 3.1 Rating cause-effect relationships between STANDBY Process radiation monitoring system GAS TREATMENT SYSTEM and the following:

Question:

Given the following:

Standby Gas has started on a high drywell pressure STANDBY GAS SELECT switch is in the SYS 1 position Which ONE of the following describes the response of the Standby Gas Treatment System (SGTS) to a subsequent high alarm condition on BOTH Reactor Building Ventilation Exhaust Radiation channels?

A. #1 SGTS will remain operating, and #2 SGTS will automatically start B. #1 SGTS will shutdown, then SGTS #1 and #2 will re-initiate.

C. #1 SGTS will remain operating] and #2 SGTS will remain in standby.

D. #1 SGTS will shutdown then re-initiate, and #2 SGTS will remain in standby.

ANSWER: IC REFERENCE(S RAP 1OF-1-f I Procedure 330 Because of this, subsequent initiation signals will COT put the SGTS through a re-initiation sequence. Therefore:

A is incorrect because system 2 fan will secure after the initial initiation Explanation: sequence] as long as system 1 fan develops required flow within a 2 to 3 minute time period.

B is incorrect, as it will not go through a re-initiation sequence.

C is correct References to be None provided during exam:

Learning 10445 Objective Question Source Bank 1 Modified Bank I I New X Question Cognitive Memory or Fundamental Comprehensionor X Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 261000 Standby Gas Treatment System A4.03 Importance 3.0 3.0 Rating Ability to manually operate and/or monitor in Fan the control room:

0 A manual start of Standby Gas Treatment System (SGTS) is in progress 0 The STANDBY GAS SELECT switch is in SYS II position 0 All procedure prerequisites have been verified and EF-1-9 is taken to the HAND position NO other actions are taken FIVE (5) minutes later, SGTS I orifice valve, V-28-24 will be (1) and SGTS II orifice valve, V-28-28 will be 12)

. (1)

(2)

CLOSED CLOSED (1) CLOSED B.

(2) OPEN (1) OPEN c- (2) CLOSED (1) OPEN D.

(2) OPEN ANSWER: I I Procedure 330 On SGTS start, the orifice valve for the selected train will initially OPEN, but as soon as flow is established, will then close. The opposite train orifice valve will OPEN as soon as the selected train system flow low clears.

Additionally, the given sequence will have SGTS and RB HVAC in service simultaneously, but will not result in SGTS fan trip. Therefore:

Explanation:

A is incorrect, because V-28-24 will be open B is incorrect, because the valve lineups are backwards C is correct D is incorrect, because V-28-28 cannot be open once system flow has been established References to Ld None c-

Question Source Bank I Modified Bank I I New

~

X L Question Cognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis 10 CFR Part 55 Content: I I 55.41 (b) (7) I 55.43 I

Knowledge and Ability Reference Information RO SRO 262001 A.C. Electrical Distribution K1.01 Importance 3.8 4.3 Rating Knowledge of the physical connections and/or cause-effect relationships between A.C. Emergency generators (dieseVjet)

ELECTRICAL DISTRIBUTION and the following:

Given the following:

0 The plant is at 100% power and steady 0 At time T=O seconds, Annunciator T-3-a, BUS C VOLTS LO is received Bus 1C is reading 3750 volts Based upon these conditions, EDG #1 will fast start at time (11 and 4160V breaker 1C will trip at time (2)

(1) T=O seconds As (2) T=3 seconds (1) T=3 seconds B-(2) T=3 seconds (1) T=3 seconds c- (2) T=lO seconds (1) T=l 0 seconds D.

(2) T=l seconds I RAP T-3-a I RAPT-4-a I [ref #3]

For low voltage (e3830 volts per RAP T-3-a), the low voltage condition must be present for 10 seconds before the EDG gets a fast start signal, and breaker 1C will trip. For 10-10 voltage (0 volts per RAP T-4-a), the EDG will fast start after 3 seconds and breaker 1C will trip. Therefore, since this is a low voltage condition:

Explanation: A is incorrect, because the timer starts upon receipt of the alarm, and both actions happen in 10 seconds B is incorrect for the low voltage condition, but is correct for 0 voltage condition C is incorrect, as EDG 1 will not fast start until 10 seconds D is correct References to I> None Learning 01086,01087 0bjective

Question Source Bank I Modified Bank I I New X u Question Cognitive

- Memory or Fundamental I X I Comprehension or I Level: I Knowledae I I Analvsis I I I 10 CFR Part 55 Content: I 55.41 I (b) (7) I 55.43 I I I

Knowledge and Ability Reference Information RO SRO 262001 A.C. Electrical Distribution A2.01 Importance 3.4 3.6 Rating Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to Turbine/generator trip correct, control, or mitigate the consequences of those abnormal conditions or operations:

Reactor power is steady at 25%, and a plant shutdown IAW Procedure 203 must be A

commenced.

Reactor power is less than 25%, and a plant shutdown IAW Procedure 203 must be commenced. r r ~ L~/;1sr- * ~ ~

C. Reactor power is steadv at 25%,?kda. reactor3t- e initiam IAW ABN-1.

D. I Reactor power is less than 25%. and a reactor scram must be initiated IAW ABN-1.

I Procedure 337 I ABN-2 A turbine trip under these conditions will result in a loss of 4160V buses 1A and 1C, because S1B will NOT fast transfer due to a failure to reset the breaker (by leaving the switch in the red-flagged position.) Two recirc pumps will trip, requiring a reactor scram for multiple recirc pump trips IAW Explanation: ABN-2. Therefore:

A is incorrect, as power will drop due to the loss of 2 recirc pumps B is incorrect, as a normal plant shutdown is NOT appropriate C is incorrect, as power will drop due to the loss of 2 recirc pumps References to be None Learning 10445 Objective

Question Source Bank I Modified Bank I I New X Y Question Cognitive Memory or Fundamental I I Comprehension or X Level: I Knowledge I Analysis

v Knowledge and Ability Reference Information RO SRO 262002 Uninterruptable Power Supply A2.01 Importance 2.6 2.8 (A.C./D.C.) Rating Ability to (a) predict the impacts of the following on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.); and (b) based on those predictions, Under voltage use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

VMCC 1A2 power supply is 460 VAC VMCC 1B2 power supply is 250 VAC Based upon the above, the VACP-1 PWR XFER alarm on 9XF will be (11 , and we can continue operating with this condition for up to (2) before a plant shutdown is required.

(1) LIT

'J A*

(2) 7 days (1) LIT B-(2) 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months c* (2) 7EXTINGUISHED (1) days (1) EXTINGUISHED D.

(2) 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months ANSWER: lB REFERENCE(S): RAP 9XF-3-c Normal power supply to VACP-1 ATS is VMCC 182. The switch will auto transfer at 70% sensed voltage (460 V x .7= 322 VAC), therefore, the ATS will switch to the alternate source, VMCC 1A2. Whenever the switch is aligned to VMCC 1A2, the VACP-1 PWR XFER alarm is received. The normal power supply must be restored and shifted back to VMCC 1B2 Explanation: within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months , or the reactor shall be placed in cold shutdown within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . This is a GL 91-11 concern. Therefore:

A is incorrect, as 7 days is longer than 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months B is correct C is incorrect due to alarm not in and longer than 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months D is incorrect due to alarm not in References to be None provided during exam:

Learning 01085 L'

Objective

Question Source Bank I Modified Bank- I I New X v Question Cognitive Memory or Fundamental Comprehension or X Level: Knowledge Analysis 10 CFR Part 55 Content: I 55.41 1 (b) (7) I 55.43 I

Knowledge and Ability Reference Information RO SRO 263000 D.C. Electrical Distribution K4.02 Importance 3.1 3.5 Ratina Knowledge of D.C. ELECTRICAL Breaker interlocks, permissives, bypasses]

DISTRIBUTION design feature(s) and/or and cross ties interlocks which provide for the following:

Question:

Given the following:

0 The plant is at 100% power Both RWCU pumps are in service due to high sulfates A total loss of DC Distribution Center C (DC-C) occurs The RWCU System will . . .

A. 1 isolate. and RWCU DumD A will t r b B. 1 isolate. and RWCU DumD B will trb C.- NOT isolat& and RWCU pump A will trip D. NOT isolate, and RWCU pump B will trip actuation on loss of DC-F (fed from DC-C): but breaker control power for the RWCU pump A comes from DC-C, so RWCU pump A breaker cannot trip. RWCU pump B will trip, as its breaker control power is DC-B.

Therefore:

Explanation: A is incorrect, as RWCU pump A has no breaker control power B is correct C is incorrect] as RWCU isolates on low flow and high NRHX outlet temp signals due to loss of DC-F power, and pump will not trip D is incorrect] as RWCU isolates on low flow and high NRHX outlet temp signals due to loss of DC-F power References to I ? I None Learning 01 127,10445 0bjective Question Source Bank 1 Modified Bank I I New X Question Cognitive Memory or Fundamental Comprehensionor X Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 263000 D.C. Electrical Distribution A3.01 Importance 3.2 3.3 Rating Ability to monitor automatic operations of the D.C. Meters, dials, recorders, alarms, and ELECTRICAL DISTRIBUTION including: indicating lights 8W9F indicate-asfollows:

Line 1 (+) lamp is EXTINGUISHED Line 2 (-) lamp is BRIGHTLY LIT This indicates a ground on (1I and the GROUND DETECTED red light on the C1 Battery Charger will be (2) or these conditions.

(1) Line 1 (+)

A.

(2) LIT (1) Line 2 (-)

B.

(2) LIT (1)

- Line 1 (+)

b.

(2) EXTINGUISHED (1) Line2 (-)

ANSWER: IC REFERENCE(S): RAP U-4-f, pg. 2 I indicating lights are ON when there is no problem, and go OUT to indicate the problem. Therefore:

References to be None Learning 10446 0bjective

Question Source Bank I Modified Bank 1 I New X Question Cognitive Memory or Fundamental I I Comprehension or X Level: I Knowledge I Analysis

Knowledge and Ability Reference Information RO SRO 264000 Emergency Generators K3.01 Importance 4.2 4.4 (DieseVJet) Rating malfunction of the EMERGENCY GENERATORS (DIESEUJET) will have on I Emergency core cooling systems the following:

Question:

Given the following:

Drywell pressure is 3.5 psig and rising Breaker S1A failed to close when the Main Generator tripped 0 One (1) minute later, the #1 EDG Cooling Water Pump fails, causing an Engine Cooling Water Temperature High condition All other equipment operates as designed If no operator action is taken, which of the following explains the response of the Core Spray system and the EDG?

NZOlA and NZ03A will ...

A. I trip due to EDG trip on Hi Temp AND NZOl C will automaticallv start B. 1 trip due to EDG trip on Hi Temp. AND NZOlC will NOT automaticallv start C. I run until diesel failure occurs AND NZOlC will automaticallv start D. I run until diesel failure occurs. AND NZOl C will NOT automaticallv start I

I RAP T-4-b

1 EDG will fast start under these conditions due to UV. Therefore, Engine Temperature (ET) trips are bypassed. When #1 EDG eventually fails, bus I C will deenergize, and the backup CS main pump (NZOlC) will automatically start when system 1 pressure drops below 100 psig. NZ03C Explanation: will NOT start due to interlock. Therefore:

A is incorrect, as the EDG will NOT trip on ET B is incorrect, as the EDG will NOT trip on ET C is correct D is incorrect, as NZOl C will start References to be None

Question Source Bank I Modified Bank I 1 New [XI b Question Cognitive Memory or Fundamental I 1 Comprehensionor -[XI-Level: I Knowledge I Analysis

Knowledge and Ability Reference Information RO SRO 300000 Instrument Air G 2.1 2 3 Importance 3.9 Rating The reactor is operating at 100% power 0 1-1 air compressor is the LEAD compressor 1-2 air compressor is the LAG compressor 0 1-3 air compressor is available A loss of USS 1Al occurs Service Air pressure lowers to 78 psig Based on the above conditions, what action is required?

A. I Confirm ONLY 1-2 comDressor is running IAW ABN 35, Loss of Instrument Air I

B. Confirm 1-2 and 1-3 comDressors are runnina IAW ABN 35. Loss of4nstfument Air.

C. Isolate dryers, pre-filters and post-filters IAW M-cb, RCVR 2 / INST AIR PRESS LO D. Verify Service Air Valve, V-6S-2, is isolated IAW M-2-b, SVC AIR DISCH VLV CLOSED ANSWER: 16 REFERENCE(S): ABN-35 1

[ M-2-b, M-3-b, M-7-b [ref #3]

References to be provided None [ref prv #2]

during exam:

Question Source Bank I Modified Bank I I New [XI Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (10) 55.43 Content:

Question # I 5 2 Examination Outline Cross-reference Level I RO I Tier # 12 I Group# I 1 Knowledge and Ability Reference Information RO SRO 300000 Instrument Air K5.01 Importance 2.5 Ratina Knowledge of the operational implications of the following concepts as Air Compressors they apply to the Instrument Air:

Given the following:

$I #3 air compressor is out of service.

i. #1 air compressor trips fyb#2 air compressor does NOT start.

e Instrument Air pressure is 52 psig and lowering NO control rods have moved.

Based on the above conditions, what action is required?

A. Scram the reactor immediately IAW ABN-35, Loss of Instrument Air B. Press the Remote Start switch for #1 air compressor IAW alarm response M-5-a C. Scram the reactor after two or more rods move in IAW ABN-35, Loss of Instrument Air D. Press the Remote Start switch for #2 air compressor IAW alarm response M-5-b ANSWER: / A REFERENCE(S): ABN-35 I [ref #2] I [ref #3]

I D is incorrect, Remote Start switch is not used under these conditions.

References to be provided I None I [ref prv #2]

Learning 10450 Objective Question Source Bank I Modified Bank [XI I I New Question Cognitive Memory or Fundamental [X] Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (IO) 55.43 Content:

.-.--- Question # 52 1 Examination Outline Cross-reference Knowledge and Ability Reference Information RO SRO 300000 Instrument Air K5.01 Importance 2.5 Ratina Knowledge of the operational implications of the following concepts as Air Compressors thev amlv to the Instrument Air:

Question:

Given the following:

0 #1-3 air compressor is out of service.

1-1 air compressor trips

1-2 air compressor does NOT start.

Instrument Air pressure is 52 psig and lowering NO control rods have moved.

Based on the above conditions, what action is required?

A. I Scram the reactor immediatelv IAW ABN-35. Loss of Instrument Air B. I Press the Remote Start switch for #1-1 air comwessor IAW alarm resDonse M-5-a C. I Scram the reactor after two or more rods move in IAW ABN-35. Loss of Instrument Air

. I V'

ANSWER: ] A REFERENCE(S): ABN-35 1 [ref #2] I [ref #3]

References to be provided None [ref prv #2]

during exam:

Learning 10450 Objective Question Source Bank 1 Modified Bank [XII I New Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (10) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 400000 Component Cooling Water G 2.4.4 Importance 4.0 System Rating The plant is operating at rated power when the following occurs:

0 The TBCCW DISCH PRESS LO alarm actuates.

The TBCCW SURGETANK LVL HVLO annunciator alarms.

0 All TBCCW pumps are running.

TBCCW surge tank level is confirmed to be low What action is required?

A. I Scram the reactor and execute ABN-1, Reactor Scram B. I Commence a normal Dlant shutdown IAW Drocedure 203. Plant Shutdown C. Perform a rapid power reduction IAW procedure 202.1, Power Operations Maximize TBCCW flow IAW procedure 309.1, Turbine Building Closed Cooling Water D.

System REFERENCE(S): I ABN-20 I RAP Q-1-f I [ref #3]

1 A is the correct answer IAW ABN-20.

References to be provided None [ref prv #2]

during exam:

Learning 10450 Objective Question Source Bank I I Modified Bank [XI I New Question Cognitive Memory or Fundamental [XI Comprehensionor Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (10) 55.43 Content :

Knowledge and Ability Reference Information RO SRO 201001 Control Rod Drive Hydraulic Al.06 Importance 3.4 3.4 System Rating Ability to predict and/or monitor changes in parameters associated with operating the Control HCU pressure/level Rod Drive Hydraulic System controls including:

Reactor Power is 100%

0 Alarm H-8-c, ACCUMULATOR PRESS LO/LEVEL HI, comes in for HCU 38-15 0 The local test switch is depressed for HCU 38-15 and the light remains ON Based on the above, the alarm is due to (1 and rod scram time will be (2)

A.

(1) low pressure (2) slower 6.

(1) high water level (2) slower C.

(1) low pressure (2) the same D.

(1) high water level (2) the same I

REFERENCE(S): I RAP H-8-c I [ref #2] I [ref #3]

If the light goes out the alarm is due to high level, if the light stays on it is due to low pressure. With lower accumulator pressure, scram times will be slower.

Explanation:

A is the correct answer, CRD scram pressure will be lower, scram time will be slower.

B is incorrect, it is not due to high level.

C is incorrect, scram time will be slower.

References to be provided None [ref prv #2]

during exam:

Learning 02419,10449 0bjective

Question Source Bank I I Modified Bank [XI I New Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledge AnaIysis 10 CFR Part 55 55.41 (b) (6) 55.43 Content:

Question # I 55 Knowledge and Ability Reference Information RO SRO 202001 I Recirculation Svstem I A4.01 I Importance 3.7 I Rating Ability to manually operate and/or monitor in the Recirc pumps control room Question:

Given the following:

During power operation, the A recirc pump is tripped due to high vibration The Unit Reactor Operator attempts to close the A recirc pump discharge valve The A recirc pump discharge valve will NOT close What is the NEXT required action?

A. I lmmediatelv commence a normal Dlant shutdown B. I Close the discharae valve from its MCC C. I Close the mmc) suction valve from Panel 3F ANSWER: IC REFERENCE(S): ABN-2 I [ref #2] I [ref #3]

References to be provided None [ref prv #2]

during exam:

Learning 10450 0bjective Question Source Bank [ Modified Bank [XI I I New Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (10) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 202002 Recirculation Flow Control K6.01 Importance 2.8 System Rating Knowledge of the effect that a loss or malfunction of the following will have on the Recirculation Flow A.C. power Control System:

Plant is operating at 100% power DCC-X computer is CONTROLLING DCC-Y computer is 00s Power to the DCC-X computer fails What is the effect on the Recirculation Flow Control System?

A. I Recirc flow lowers to minimum B. I The recirc pump scoop tubes lockup C. 1 Control is transferred to the Moore Stations ANSWER: (c REFERENCE(S): RAP J-1-C I [ref #2] I [ref #3]

References to be provided None [ref prv #2]

during exam:

Learning 00226 Objective Question Source Bank I I Modified Bank [XI I New Question Cognitive Memory or Fundamental [XI Comprehensionor Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 214000 Rod Position Information System K5.01 Importance 2.7 Rating Knowledge of the operational implications of the following concepts as they apply to the Rod Reed switches Position Information System:

Given the following:

0 Plant is conducting rod swaps at 90% power 0 A control rod is driven from position 4 8 to position 3 8 0 Reactor power lowers as the rod is inserted 0 The Rod Control switch is released as the rod passes position 3 9 0 Upon release of the Rod Control switch the rod position display indicates black-black 0 Reactor power remains steady when the Rod Control switch is released What has occurred?

A. I The rod is uncouded B. I The rod is at gosition 0 0 C. I The reed switch has failed ANSWER: IC REFERENCE(S): 235 I [ref #2] I [ref #3]

A is incorrect, rod is still coupled (change in power).

B is incorrect, the rod is still at 38 (power has not continued to lower)

Explanation: C is the correct answer, if the reed switch is stucWfailed it will not indicate the position.

D is incorrect, the rod would indicate 39.

References to be provided None [ref prv #2]

during exam:

Learning 00726 0 bjective Question Source Bank I Modified Bgnk I I New [XI Question Cognitive Memory or Fundamental nsion or -4 XI Level: Knowledge 10 CFR Part 55 55.41 (b) (7) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 215001 Traversing In-Core Probe K4.01 Importance 3.4 Rating Knowledge of Traversing In-Core Probe design Feature(s) and or interlock(s) which provide Primary Containment Isolation For the following:

While an operator is inserting a TIP into the core, a containment isolation signal is received.

The TIP purge valve shuts and the TIP ...

drive automatically shifts to reverse and withdraws the detector to the in-shield position A.

and the shear valve fires drive automatically shifts to reverse and withdraws the detector to the in-shield position B.

and the ball valve closes shear valve fires to cut the detector cable and seal the guide tube. The detector does not c' withdraw to the in-shield position ball valve closes cutting the detector cable and sealing the guide tube. The detector does D.

not withdraw to the in-shield position Procedure 405.2, [ref #21 REFERENCE(S): [ref #3]

312.9 B is the correct answer, IAW 405.2.

Explanation:

C is incorrect, the detector will withdraw before isolating the tube.

References to be provided None [ref prv #2]

during exam:

Learning 10444 0 bjective Question Source Bank I [XI I Modified Bank I I New Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (7) 55.43 Content:

v Knowledge and Ability Reference Information RO SRO 215001 ' Traversing In-Core Probe K4.01 Importance 3.4 Rating Knowledge of Traversing In-Core Probe design feature(s) and or interlock(s) which provide Primary Containment Isolation for the following:

While an operator is inserting a TIP into the core, a containment isolation signal is received.

The TIP purge valve (1) and the TIP (2)

(1) remains open A. (2) drive automatically shifts to reverse, withdraws the detector to the in-shield position and the ball valve closes.

(1) shuts

6. (2) drive automatically shifts to reverse, withdraws the detector to the in-shield position and the ball valve closes.

(1) remains open

c. shear valve fires to cut the detector cable and seal the guide tube.

'W (2)

(1) shuts D. shear valve fires to cut the detector cable and seal the guide tube.

(2)

Procedure 405.2, REFERENCE(S): [ref #21 [ref #3]

312.9 References to be provided None [ref prv #2]

during exam:

Learning 10444 Objective Question Source Bank I [XI I Modified Bank I I New Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (7) 55.43 Content:

~- ~-

Question # I 59 ~~~ ~ ~~ ~ ~ ~~~ ~ ~

Knowledge and Ability Reference Information RO SRO 219000 Torus/Suppression Pool Cooling K2.02 Importance 3.1 Mode Rating Given the following:

Containment Spray pump 51C and ESW pump 52C are in the Torus Cooling Mode T-2-e, MN BRKR 1D 86 LKOUT TRIP, is received Containment Spray/ESW pumps.. .

A. I 51C and 52C remain oPeratina. 51A and 52A will be available as backum ~~ ~-

B. 51C and 52C remain operating. 51D and 52D will be available as backups C. 51 C and 52C trip. 51A and 52A will be available as backups D. 51C and 52C trip. 51D and 52D will be available as backups REFERENCE(S): I Proc. 341, Att. 6 1 [ref #2] [ [ref #3]

I 51/52 A and B are powered from bus IC, 51/52 C and D are powered from I bus 1D. [unlike Coie Spray power supplies]

A is incorrect, 51C 52C will trip.

Explanation:

B is incorrect, 51C 52C will trip and 51D 520 will have no power.

References to be provided None [ref prv #2]

during exam:

Learning 10444 0bjective Question Source Bank I Modified Bank 1 I New [XI Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (7) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 223001 Primary Containment System and A2.10 Importance 3.6 3.8 Auxiliaries Rating Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the High drywell temperature consequences of those abnormal conditions or operations.

The plant is operating at 100% power The supply breaker for MCC 1A23 has tripped on instantaneous overcurrent The 1-4 and 1-5 Drywell Cooling fans have been verified running RBCCW flow to the drywell has been maximized 0 The DW TEMP HI alarm, C-8-h is alarming and will NOT clear The STA has confirmed the alarm is valid Based upon the above, Bulk drywell temperature is approximately (11 and you are required to (2) ?

(1) 150deg. F A.

(2) Enter Primary Containment Control ONLY (1) 281 deg. F B- Enter Primary Containment Control, AND scram the reactor IAW ABN-1 (2)

(1) 150deg. F c- (2) Enter Primary Containment Control, AND commence a plant shutdown IAW 203.1 (1) 281 deg. F D. (2) Enter Primary Containment Control, RPV Control - No ATWS, AND Perform an I Emergency Depressurization ANSWER: IC II REFERENCE(S I RAPC-8-h This alarm indicates bulk drywell temperature is above 150 deg. F. Actions listed are to enter Primary Containment Control, and commence an orderly plant shutdown IAW procedure 203,l.Therefore:

A is incorrect because no mention of plant shutdown Explanation: B is incorrect because the alarm is not indicative of approaching design temperature of 281 deg. Also, a scram is not required C is correct D is incorrect because the alarm is not indicative of approaching design temperature of 281 deg. Also, ED is not required wovided during exam:

Learning 03000,03002 Objective

- Question Source Question Cognitive Bank I Modified Bank Memory or Fundamental I I I I New Comprehension or X

X

Knowledge and Ability Reference Information RO SRO 233000 Fuel Pool Cooling/Cleanup A3.02 Importance 2.6 Rating Ability to monitor automatic operations of the Fuel Pump trip(s)

Pool Cooling/Cleanup including:

Question:

Given the following:

Fuel Pool system is operation with one pump running The fuel pool filter keylock switch in ORW is in the BYPASS position G-7-a, SKMR SRG TANK LVL LO-LO, alarm comes in What will be the effect on the Fuel Pool Cooling system?

A. The fuel pool makeup valve opens B. The fuel pool pump trips on low flow C. The fuel pool pump trips on low surge tank level D. The low surge tank level pump trip is bypassed G-7-a, Procedure REFERENCE(S): [ref #21 [ref #3]

311 References to be provided None [ref prv #2]

during exam:

Learning 08570,10441 Objective Question Source Bank I Modified Bank [XI I 1 New Question Cognitive Memory or Fundamental Comprehension or [XI Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (7) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 245000 Main Turbine Generator and K3.08 Importance 3.7 3.8 Auxiliary systems Rating Knowledge of the effect that a loss or malfunction pressure control of the Main Turbine Generator and Auxiliary system systems will have on the following:

Given the following:

The plant is operating at 100% power A leak develops in the vacuum sensing bellows for "B"main condenser On control room panel 5F/6F, the indicated vacuum for "B"condenser goes from 28.7 to 12 in. Hg How will the main turbine respond?

A. The turbine will NOT trip, the turbine bypass valves will NOT open B. The turbine will NOT trip, the turbine bypass valves will open C. The turbine will trip, the turbine bypass valves will NOT open D. I The turbine will trip, the turbine bypass valves will open ANSWER: ID REFERENCE(S): RAP Q-2-c I [ref #2] I [ref #3]

Explanation:

B is incorrect, turbine will trip.

C is incorrect, the bypass

.. will still open greater

- than 10 in. Hg. -

1 D is correct,.

References to be provided 1 None I [ref prv #21 Learning 10444,01723 Objective Question Source Bank 1 Modified Bank [XI I I New Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (7) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 256000 Reactor Condensate system G 2.1.28 Importance 3.2 Ratina Knowledge of the purpose and function of major system components and controls Question:

Condensate system flow of 2400 gpm provides for:

A. Minimum flow through LP heater AND cooling for SJAE condensers B. Maintaining LP Drain Cooler level AND cooling for steam packing exhauster Minimum flow for condensate pumps AND cooling for SJAE condensers and steam C.

packing exhauster Maintaining LP Drain Cooler level AND cooling for SJAE condensers and steam packing D.

exhauster ANSWER: IC REFERENCE(S): FSAR, I [ref #2] I [ref #3]

A is incorrect, does not provide flow for LP heater.

B is incorrect, does not provide drain cooler level.

W Explanation: C is the correct answer, provides for condensate pump min flow, cooling for SJAE condensers, provides cooling for SJAE condensers.

D is incorrect, does not provide drain cooler level.

during exam:

Learning I 10435 Question Source Bank I Modified Bank [XII I New Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (4) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 259001 Reactor Feedwater System K1.08 Importance 3.6 Rating cause-effect relationships between Reactor Feedwater System and the 1 Reactor water level control system following:

Question:

Given the following conditions:

Plant is operating at 65% power 0 Master feedwater controller in "AUTO",setpoint is 163.5 in. TAF 0 Feedpump 1A is running with its flow controller in "AUTO" 0 Feedpump 1B is running with its flow controller in "MAN" 0 The flows in the operating feed strings are equal With the Master feedwater controller selected to the " S display, the adjustment knob is rotated in the COUNTER-CLOCKWISE direction.

What will occur?

A. I Reactor level setDoint is lowered, the A and B MFRVs will close B. I Reactor level setpoint is lowered, ONLY the A MFRV will close C. 1 Reactor level setDoint is raised, the A and 6 MFRVs will oDen ANSWER: IB REFERENCE(S): Procedure 317 I [ref #2] I [ref #3]

A is incorrect, the B MFRV does not move.

B is the correct answer, the setpoint is lowered and the B MFRV does not Explanation: move.

C is incorrect, the setpoint is lowered.

D is incorrect, the setpoint is lowered.

References to be provided None [ref prv #2]

during exam:

Learning 10447 0 bjective Question Source Bank I [XI I Modified Bank I I New Question Cognitive Memory or Fundamental Comprehensionor [XI Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (7) 55.43 Content:

Knowledge and Ability Reference Information RO SRO 272000 Radiation Monitoring System Al.01 Importance 3.2 3.2 Rating Ability to predict and/or monitor changes in parameters associated with operating the Lights, alarms, and indications RADIAT10N MONIT0R ING SYSTEM controls associated with normal operations including:

Given the following conditions:

The Plant is operating at 100% power Channel B Off-gas radiation monitor failed downscale last shift Channel A Off-gas radiation monitor indicates 1100 mr/hr at 1015 hours0.0117 days 0.282 hours 0.00168 weeks 3.862075e-4 months Off-gas bypass valve V-7-31 will.. .

A. I oDen AND the Off-nas svstem will isolate at 1030 B. remain closed AND Off-gas system will isolate at 1030 C. open AND Off-gas system will NOT isolate A is incorrect, as it will not open Explanation: B is correct C is incorrect, as it will not open AND off gas will isolate D is incorrect, as off gas will isolate References to be None Learning 00666 0bjective Question Source Bank I Modified Bank [ 1 New X Question Cognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis

Question # 1 66 Examination Outline Cross-reference Level I RO I Tier # I 3 [ Group# 11 Knowledae and Abilitv Reference Information IRO l S R 0 2.1 Conduct of operations 2.1.2 Importance 3.0 4.0 Rating An RO left shift work on 9/1/2004 and was placed in a day shift assignment The RO had worked all previously scheduled days as a reactor operator until leaving shift Since leaving shift, the RO has performed license duties as follows:

9/4/2004; 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 10/1/2004; 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Which of the following is correct?

A. The operators license is inactive on 10/1/2004.

6. The operators license is inactive on 12/1/2004.

The operator must stand at least 3 additional 12-hour shifts before 11/30/2004 to c* maintain an active license.

The operator must stand at least 4 additional 12-hour shifts before 12/31/2004 to A minimum of 7 8-hour shifts or 5 12-hour shifts per calendar quarter is required. Therefore:

A is incorrect, as the license is still active Explanation: B is incorrect, as the license is still active C is incorrect, as the requirement is per calendar quarter, not per running 3-month time frame D is correct References to be None Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis

b Knowledge and Ability Reference Information RO SRO 2.1 Conduct of operations 2.1.33 Importance 3.4 4.0 Rating The Plant is at 100% power At 0700 on 10/1/04, unidentified leak rate was 2.2 gpm At 0300 on 10/2/04, unidentified leak rate is 4.7 gpm What action is required A. I Place the reactor in the shutdown condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

B. Place the reactor is the cold shutdown condition within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Reduce the leak rate below the allowable limit within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or place the reactor in the C. shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and be in the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c Identify the source of leakage within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or be in the shutdown condition within the Dm next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and be in the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ANSWER: ID REFERENCE(S:: T.S. 3.3.0.3 B is incorrect because this is the action to take if there are no T.S. LCO for Explanation: the condition (LCO 3.0.A)

References to be TS 3.3 Learning 10451 Objective Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental I X I Comprehension or Level: I Knowledge I Analysis

Knowledge and Ability Reference Information RO SRO 2.1 Conduct of operations 2.1.31 Importance 4.2 3.9 Rating If the 1-3 Air Compressor is operating as the LEAD compressor and the 1-1 Air Compressor is operating as the LAG compressor, the 1-3 local select switch will be in the (1) position AND the 1-1 Air Compressor will start when air header pressure reaches (2) psig.

the 90 psig is for the 1-3 compressor to start when it is the lag compressor B is incorrect, as the select switch does not have LEAD as a position C is incorrect, as the 90 psig is for the 1-3 compressor to start when it is the

Question # I 69 I Examination Outline Cross-reference Level I RO I Tier # I3 I Grout,# 12 Knowledge and Ability Reference Information 2.2 Equipment control 2.2.1 lmportance 13.7 Rating reactivity.

Question:

Given the following:

0 A reactor startup is in progress NO control rods have been withdrawn Initial SRM counts are:

SRM21 = ~ O C P S SRM 22 = 45 CPS SRM 23 = 50 GPS SRM 24 = 55 CPS Which of the following will require completely notch withdrawing control rods until the reactor is critical and adding heat to the coolant?

A. When SRM 24 = 440 cps B. When SRM 21 = 600 cps C. I The reactor is not critical after reaching the +1% dk sequence step in the ECP.

I D. The reactor is not critical after the first four control rod groups have been withdrawn.

ANSWER: ID Procedure 201, REFERENCE(S):

step 6.24 A is incorrect, as 3 doublings only requires notch withdrawal between position 06 and 24 B is incorrect, as greater than 3 but less than 4 doublings only requires Explanation: notch withdrawal between position 06 and 24 C is incorrect, as the startup must stop and Reactor Engineering has evaluated the discrepancy and provided further instructions D is correct References to be None Learning 10447 Obiective

Question Source Bank I Modified Bank I I New X

-u Question Cognitive Memory or Fundamental I I Comprehension or X Level: I Knowledge I Analysis c

Knowledge and Ability Reference Information RO SRO 2.2 Equipment Control 2.2.13 Importance 3.6 3.8 Rating A. Sub Clearance B. Clearance Exception C. Temporary Clearance ANSWER: ID REFERENCE(S) : OP-MA-109-101 References to be None Learning C&T lesson plan - obj. #36 0biective I 1 I

~ ~~

Question Source Bank Modified Bank New X Question Cognitive

- Memory or Fundamental I X I Comprehension or Level: I Knowledge I Analysis c

Question # I 71 Examination Outline Cross-reference Level 1 RO 1 Tier # 13 I Group# 12 Knowledae and Abilitv Reference Information I R O ISRO 2.2 Equipment Control 2.2.2 Importance 4.0 3.5 Rating Given the following:

The plant is at 60% power and stable The 6 Recirc loop is idle, all other recirc loops are operating in AUTO 0 All prerequisites have been met to start the B Recirc pump 0 The B MG Set Drive Motor breaker is shut The B MG Set scoop tube is at 100%

0 The WARM LIGHT for the B Recirc MG Set has just illuminated When the 6 Recirc Pump STRT/NORM pushbutton is depressed . . .

A. I the field breaker will close immediately, and the SCOOD tube will remain at 100%.

B. I the field breaker will close immediately, and the SCOOD tube will start running back.

the scoop tube will start running back, and the field breaker will close when the scoop

c. tube passes through the 60% to 50% range.

the scoop tube will start running back, and the field breaker will close when the scoop Dm tube Dasses throuah the 40% to 30% ranae.

A is incorrect, as the field breaker will not close if scoop tube position is beyond approximately 40%

B is incorrect, as the field breaker will not close if scoop tube position is Explanation: beyond approximately 40%, plus the sequence is out of order C is incorrect, as the field breaker will not close if scoop tube position is beyond approximately 40%

D is correct References to be None Learning 10447 Objective Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis

2.3 Radiation Control 2.3.10 Importance 2.9 3.3 I

Rating Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure..

Question:

Given the following:

0 You are assigned work in a radiation area 0 You exposure limit is 100 mrem 0 The dose rate in the work area is 30 mr/hr 0 Your assignment will take 90 minutes to complete.

10 minutes after entering the work are, your ESRD begins to chirp/beep.

What action is required?

~~

A. I Monitor the dose rate on vour ESRD. continue to work I Warn other workers. exit the area, notifv Rad Pro

~ ~~

B.

C l Wait for vour exDosure limit to be reached, then exit the area 1

~

D. Complete the work assignment, exit the area, notify Rad Pro I

ANS\ n-REFERENCE(S):

IrGuide, pg. i o 9 I A is incorrect, must leave the area I C is correct, incorrect, must leave the area due to unexpected rad levels References to be None Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis

W Knowledge and Ability Reference Information RO SRO 2.3 Radiation Control 2.3.4 Importance 2.5 3.1 Rating In order to exit the RCA, you must.. .

W REFERENCE(S):

recount one more time with the same monitor, and if no alarm then exit the

Knowledge and Ability Reference Information RO SRO 2.3 Radiation Control 2.3.4 Importance 2.5 3.1 Rating Given the following:

A plant transient has occurred 0 Radiation levels in the Reactor Building have forced an evacuation of the Reactor Building 0 The reactor did NOT scram due to an electrical ATWS 0 All attempts to insert control rods from the Control Room have been unsuccessful 0 It is decided the Scram Air Header must be vented in order to insert control rods What is the MAXIMUM emergency exposure limit allowed under these conditions?

A. 2,000 mrem TEDE

6. 5,000 mrem TEDE C. 10,000 mrem TEDE 1 TEDE I

REFERENCES I RP-AA-203 I I This situation covers emergency exposure limits to an individual to protect valuable property. Since no indications are given of off-site dose, it cannot be surmised that protecting large populations is involved. The limit for protecting valuable property is 10 rem TEDE (10,000 mrem). Therefore:

Explanation: A is incorrect as that is the Administrative Dose Control level B is incorrect as that is the federal limit C is correct D is incorrect, as that is the limit for lifesaving or protecting large Dor>ulations References to be None Learning Rad Worker training lesson plan, obj. 17 0bjective Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO G 2.4.6 importance 3.1 Rating A. I Torus to Drwvell vacuum breakers I

6. Standby gas treatment system C. Reactor building to Torus vacuum breakers D. Containment spray pumps ANSWER: ID REFERENCE(S): EOP bases 1 [ref #2] I [ref #3]

References to be provided None [ref prv #2]

during exam:

Learning 09546 Objective Question Source Bank I [XI 1 Modified Bank I I New Question Cognitive Memory or Fundamental [XI Comprehension or Level: Knowledge Analysis 10 CFR Part 55 55.41 (b) (10) 55.43 Content:

c

Knowledge and Ability Reference Information RO SRO 2.4 Emergency Procedures / Plan 2.4.31 Importance 3.3 3.4 Rating Given the following:

A small LOCA is in progress Containment Spray System 1 is in the Drywell Spray mode Containment Spray Pump 51A and ESW Pump 52A are operating Drywell pressure is 10 psig and dropping slowly Containment Spray SYSTEM 1 FLOW LO alarm (B-2-a) is received What action occurs as a result of this alarm?

A. I Torus SDrav Valve V-21-18 automatically closes.

B. I Containment SDrav Pumr, 51A automatically triDs.

C. Containment Spray Pump 51A must be manually tripped.

D. Containment Spray System 1 automatically shifts to Torus Cooling mode.

L ANSWER: ( A REFERENCE(S): RAP B-2-a A is correct 6 is incorrect, as 51A only trips on overload or low DW press (.6 psig)

Explanation: C is incorrect, as RAP directs starting additional pumps as required D is incorrect, as automatic shift to Torus Cooling will only occur on loss of power to logic (DC-F)

References to be None Learning 10444 Objective Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental Comprehension or X Level: Knowledge Analysis t

Knowledge and Ability Reference Information RO SRO 295003 Partial or Complete Loss of AC AA2.04 Importance 3.7 power Rating The reactor is at 100% power Main breaker 1A trips as a result of a 1A bus fault.

One minute after the trip of Bus 1A, what USSs will be energized and what action is required?

ONLY USS 1A1 and 1A2 will be energized. Reenergize 1A3 IAW ABN-46, Loss of USS A- l 1..

A ..-7 ONLY USS 1A2 and 1A3 will be energized. Reenergize 1A1 IAW ABN-44, Loss of USS B.

1A1 ONLY USS 1Al and 1A3 will be energized.. Reenergize 1A2 IAW ABN-45, Loss of USS C.

1A2 USS 1A1, 1A2 and 1A3 will be energized. Check for relay targets at main breaker 1A D.

IAW S-2-e, MN BRKR 1A 86 LKOUT TRIP.

ANSWER: ~ 16- t -

I REFERENCE(S): I S-2-e I [ref #2] I [ref #3]

1 A is incorrect. 1A1 P breaker opens and 1A1 will not be energized - by the EDG Explanation: B is the correct answer. Both 1A2 and 1A3 will be energized by the EDG C is incorrect. 1Al will not be energized by the EDG D is incorrect. 1Al will not be energized by the EDG References to be provided None [ref prv #2]

during exam:

Learning 01086,01087 Objective Question Source Bank I Modified Bank I [XI I New Question Cognitive Level: Memory or Fundamental [XI Comprehension or Knowledge Analysis 10 CFR Part 55 Content: I 55.41 1 I 55.43 (b) (5)

L Question# I SO2 Examination Outline Cross-reference Level I SRC) I Tier #

Knowledge and Ability Reference Information 12 I Grout,# 12 -

259001 I Reactor Feedwater I G 2.1., / T Importance I 1 Rating Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation Question:

The plant is operating at 90% power with the following conditions:

e Power ascension using recirculation flow is in progress.

e Feedwater pumps A, B and C are in service One minute later Feedwater Pump C trips and the following alarms are reqeived:

e FEED PUMP TRIP C, (J-1-f) e FEED PUMP OL C,(J-2-f)

A. Manually scram the reactor IAW ABN-1, Reactor Scram.

B. Restart the C Feedwater r,umr, IAW J-1-f. Feed Pumr, Trir,.

C. Perform a rapid power reductionTAW 202.1, Power Operation.

D Take manual control of feedwater and restore RPV level IAW ABN-17, Feedwater System Abnormal Condition.

REFERENCE(S):

J-1-f, H-7-e, ABN-I [ref #21 I [ref #3]

A is incorrect, scram not required, reduction in power is action.

B is incorrect, C feed pump cannot be restarted due to pump OL.

Explanation: C is the correct answer, power reduction is required action.

D is incorrect, feed control does not have to be placed in manual.

References to be provided None [ref prv #2]

during exam:

Learning 10450 Objective Question Source Bank I Modified Bank I I New [XI Question Cognitive Level: Memory or Fundamental [XI Comprehension or Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I I 55.43 (b) (5)

L Knowledge and Ability Reference Information RO SRO 295006 SCRAM AA2.03 Importance 4.2 Ratina Ability to determine and/or interpret the following as Reactor water level they apply to SCRAM:

Question:

Given the following:

Plant at 100% power Digital Feed Level Transmitter Selection on 4F is in AUTO 0 A leak develops in the variable leg for the A level input to Digital Feed A. Level will lower leading to a scram. Execute ABN-1 , Reactor Scram B.

Level will rise leading to a turbine trip. Execute ABN-10, Turbine Trip and ABN-1 ,

Reactor Scram b.

I Level Transmitter Selection will automatically swap to the B level input. Adjust the level setpoint IAW procedure 317 Feedwater System Level Transmitter Selection will substitute 160 in. for input to Digital - Feed. Monitor level U.

1 IAW procedure 202, Power Operation ANSWER: lB REFERENCElSI: 1 ABN-1 fr\ I 2000-OPS-3024.24 1 [ref #3]

For variable leg lehk5ctual level goes up, for reference leg leak actual level goes down. Since A and C share same variable and reference leg both instruments will show lower level and not result in an error signal to digital Explanation:

feed A is incorrect. Indicated level will drop, causing actual level to rise B is correct.

C is incorrect, digital feed will not see this as an error.

References to be provided None [ref prv #2]

during exam:

Learning 10450 Objective Question Source Bank I Modified Bank I [XI I New niimctinn Cnnnitivm

--a ..-..--.. ...-...- -. .

I mvml. Mmmnrv

,nr Firnrlnmmntal t,., ~.....~.........~......

I IK1 I (Inmnrmhnncinn nr 1 Analysis 1.W.. I

. ......I..._..._.

Knowledge 10 CFR Part 55 Content: I 55.41 I 55.43 1 (b) (5)

Knowledge and Ability Reference Information RO SRO 295019 Partial or Complete Loss of G 2.1 -31 Importance 3.9 Instrument Air Rating 0 Plant is operating at 100% power Instrument air header pressure lowers to 30 psig Based on the above conditions, which of the following actions can be performed from the Control Room?

A.

IC Vent Valves can be opened from panel 11F, IAW Procedure 307, Isolation Condenser System.

B.

IC Makeup valves can be operated from 5F/6F, IAW SP-11, Alternate Pressure Control Systems, Isolation Condensers.

Offaas Outlet valves can be opened from 1OXF, IAW Procedure 325, Air Extraction and OffGas System.

MFRVs can be operated by placing their controllers in MAN on 5F/6F, IAW SP-2, Feed 1

~

U.

and Condensate System.

ANSWER: IB REFERENCE(S): ABN-35 I [ref #2] 1 [ref #3]

A is incorrect. Vent valves fail closed B is the correct answer. Accumulators provide operating pressure Explanation: C is incorrect. Outlet valves fail closed D is incorrect,. MFRVs lockup. Can be operated after placing in local 1 manual control References to be provided I None I [ref prv #2]

during exam:

Learning I 00666 Question Source Bank I Modified Bank I [XI I New Question Cognitive Level: Memory or Fundamental [XI Comprehension or Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I I 55.43 (b) (5) I

Question# I SO5 I Knowledge and Ability Reference Information RO SRO 29502 1 Loss of Shutdown Cooling AA2.01 Importance 3.5 3.6 Ratina Ability to determine and/or interpret the following as Reactor water heatup,coo,down rate the apply to LOSS OF SHUTDOWN COOLING:

Question:

Given the following:

The plant is shutdown Shutdown Cooling loops A and B are in service At 9:30 AM, all RBCCW is lost, reactor pressure is 41 psig At 9 5 0 AM, reactor pressure is 70 psig Based upon the above, the heatup rate is approximately.. .

A. 28 deg. F per hour B. 35 deg. F per hour C. 84 deg. F per hour D. 105deg. F er hour I

REFERENCEB I Steam tables 1 [ref #3]

temperature is 287.9 deg. The plant has heated up 28.1 degrees in a 20-minute period.

At 70 psia, saturation temperature is 302.9 deg. At 41 psia, saturation temperature is approximately 268 deg. Therefore, if the candidate m.istakes psig for psia, the result will be approximately 35 degrees in a 20-minute Explanation: period. Therefore:

A is incorrect because it was not factored for a one-hour period.

B is incorrect, as the wrong values were determined (did not convert psig to psia) and it was not factored for a one-hour period.

C is correct D is incorrect, as the wrong values were determined (did not convert psig to psia.)

References to be Steam tables Learning 00026,00042 Objective Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental Comprehension or X Level: Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 295024 High Drywell Pressure G 2.4.50 importance 3.3 Rating T = 0 minutes; Drywell pressure rises to 3.7 psig Drywell temperature is 140 deg. F T = 1 minute; Core Spray Main pump B (NZO1B) & Core Spray Booster pump B (NZ03B) are the ONLY Core Spray pumps running All other systems responded as designed Which of the following actions is required based on the above conditions?

A. I Start NZO1A & NZ03A IAW SP-1, Primary Containment initiations and isolations B. 1 Start NZO1 D & NZ03D IAW SP-1, Primary Containment initiations and isolations C. Secure EDG #1 & #2 locally IAW procedure 341, Emergency Diesel Generators D. Maximize Drywell Cooling IAW Primary Containment Control ANSWER: IA REFERENCE(S): RAP B-1-e, I SP-1 I [ref #3]

B is incorrect, SP-1 directs one main and one booster in each system. 1D/3D are Explanation:

the same system as 1B/3B.

References to be provided None [ref prv #2]

during exam:

Learning 10450 0biective 1

~- ~-~

I I

~ ~~ ~ ~ ~~ ~ ~~~~ ~

Question Source Bank Modified Bank New [XI Question Cognitive Level: Memory or Fundamental [XI Comprehension or Knowledge AnaIysis 10 CFR Part 55 Content: I 55.41 I 55.43 1 (b\ (5\

Question # I SO7 I Knowledge and Ability Reference Information RO SRO 295025 High Reactor Pressure G 2.1.28 Importance 3.3 Rating A plant transient resulted in the following:

0 Reactor water level dropping to 100 in. above TAF for 5 seconds.

Reactor pressure spiking to 1060 psig for 2.5 seconds.

IC "A" condensate return line D/P reaching 500% for 25 seconds.

0 IC "B" steam line D/P reaching 300% for 35 seconds.

Based on the above conditions, how will the plant respond?

A. I IC "A" isolates ONLY. Enter RPV Control - No ATWS.

B. IC "B" isolates ONLY. Enter Primary Containment Control.

C. IC "A" initiates and IC "B"isolates. Enter RPV Control - No ATWS.

D. IC "B" initiates and IC "A" isolates. Enter Primary Containment Control.

ANSWER: IC REFERENCE(S): RAP C-3-b 1 [ref #2] I [ref #3]

A is incorrect. B IC isolates Explanation:

B is incorrect. A IC initiates C is the correct answer. Both ICs initiate then B IC will isolate D is incorrect. B IC isolates References to be provided None [ref prv #2]

during exam:

Learning 02030 Objective Question Source Bank I [XI I Modified Bank I I New Question Cognitive Level: Memory or Fundamental I Comprehension or rxi 10 CFR Part 55 Content: I 55.41 I 55.43 I (b) (5)

Knowledge and Ability Reference Information RO SRO 295026 Suppression Pool High Water EA2.01 Importance 4.2 Temperature Rating Ability to determine and interpret the following as they apply to Suppression Pool High Water Suppression Pool cooling Temperature Given the following conditions:

RPV water level is 75 in. TAF Drywell pressure is 1.2 psig Torus temperature is 97 deg. F 0 ALL automatic actuations and initiations have occurred Based on the above conditions, which one of the following actions satisfies ALL the requirements of 2000-EMG-3200.02, Primary Containment Control?

Operating ALL pumps.. .

A. for ONE containment spray system in the Torus Cooling mode B. for ONE containment spray system in the Drywell Spray mode C. for BOTH containment spray systems in the Torus Cooling mode D. for BOTH containment spray systems in the Drywell Spray mode ANSWER: ( A REFERENCE(S): EOP SP-25 I [ref #2] I [ref #3]

pumps on the Torus at one time Explanation:

B is incorrect, drywell spray not required.

C is incorrect, CS is running; cannot run more than 4 core spray andor containment spray pumps on the Torus at one time.

D is incorrect, drywell spray not required.

References to be provided I None I [ref prv #2]

Learning 00446 Objective Question Source Bank I Modified Bank I I New [XI Question Cognitive Level: Memory or Fundamental Comprehension or [XI Knowledge Analysis

Knowledge and Ability Reference Information RO SRO 295015 1 Incomplete Scram I G 2.4.6 1 Importance 3.1 4.0.

I Rating ,I flL3 .

Knowledge of symptom based EOP mitigation FT BP strategies . ?C oy -

Given the following:

0 The plant scrammed from 100% power r Y FP4Y'lO4Y v

0 12 rods did NOT move into the core

- /

0 All APRMs are downscale 0 IRMs indicate 50% of range 6 0 Torus Temperature is 82 degrees and steady 0 Reactor Pressure is being maintained between 850 &

0 Reactor water level is being maintained between 138 Condensate During the next 3 minutes reactor power rises to 6%.

What is the required action?

A.

Terminate and prevent all injection except boron and CRD until rea below 2%.

6. Maintain RPV water level between 138 & 175 in. TAF but as low as possi-Terminate and prevent all injection except boron and CRD until RPV water level d h p /

c' below 30 in. TAF.

D. I Maintain RPV water level between 138 & 175 in. TAF with no restrictions.

ANSWER: (c REFERENCE(S): EMG-3200.01B I [ref #2] I [ref #3]

A is correct for IeveVpower issues, but this does not meet IeveVpower conditions B is incorrect due to override dealing with power above 2% or cannot be Explanation: determined C is the correct answer.

D is incorrect due to override dealing with power above 2% or cannot be I determined References to be provided EOPs w/o entry conditions [ref prv #2]

during exam:

Learning 10450 Objective

Question Source Bank 1 Modified Bank I [XI I New u Question Cognitive Level: Memory or Fundamental I Comprehension or [XI 1 Knowledge I Analysis I

Knowledge and Ability Reference Information RO SRO 215004 Source Range Monitor A2.02 Importance 3.7 Rating Ability to (a) predict the impacts of the following on the Source Range Monitor and (b) based on those predictions, use procedures to correct, control, or SRM inop condition mitigate the consequences of those abnormal operations:

CAN continue without further action(s); the SRM Rod Block is bypassed at IRM Range 3, IAW H-A.

7-a, ROD BLOCK CANNOT continue without further action(s); the SRM Rod Block will NOT clear until IRM Range B.

8 , IAW H-7-a, ROD BLOCK C. . onlv 2 SRMs are reauired to be oDerable for StartuD. IAW CAN continue without further actionkk I 8 .

- Att. 201-2, Pre-Critical Checkoff CANNOT continue without further action(s); plant procedures will NOT allow a Startup with only 2 D.

- operable SRMs, IAW Att. 201-2, Pre-Critical Checkoff AN! WER: I I

Knowledge and Ability Reference Information RO SRO 295032 High Secondary Containment EA2.01 Importance 3.8 Temperatures Rating Ability to determine and/or interpret the following as they apply to High Secondary Containment Area temperature Temperatures A fire in the reactor building has spread from the 51 elevation to the 75 elevation. The following temperatures have been reported to the Unit Supervisor:

51 RWCU PMP RM (WEST) indicates 225 deg. F 7 75 DEMIN VAULT indicates 220 deg. F 7m~

75 PRECOAT TANK indicates 230 deg. F 95 IS0 COND (NORTH) indicates 200 d e g . f fiM Y 2 Pw!m Which of the following actions is required based on the above conditions?

A. Scram the reactor IAW RPV Control - No ATWS ONLY B.

Scram the reactor IAW RPV Control - No ATWS AND Emergency depressurize IAW Emergency Depressurization Monitor area temperatures IAW Secondary Containment Control and commence a shutdown IAW procedure 203, Plant Shutdown Shutdown RBHVAC, start SGTS IAW SP-49, Confirmation of Secondary Containment D.

initiations and isolations ANSWER: ] A REFERENCE(S): EMG-3200.11 SCC 1 [ref #2] I [ref #3]

I D is incorrect, not required.

References to be provided I EMG-3200.11 SCC 1 [ref prv #2]

during exam: I Learning 10450 Objective Question Source Bank 1 Modified Bank 1 [XI 1 New Question Cognitive Level: Memory or Fundamental I 1x1

- - I Comprehension or I Knowledge 1 Analysis 10 CFR Part 55 Content: 4 55.41 1 55.43 I (b) (5) I

Knowledge and Ability Reference Information RO SRO 295036 Secondary Containment High G 2.4.6 Importance 4.0 SumpNVater Level Rating strategies Question:

Given the following:

0 Plant is at 100% power 0 The Torus develops a leak Torus water level is 146 in.

0 Rx Bldg SW Corner Room water level is 24 in. and rising 0 Rx Bldg NW Corner Room water level is 12 in. and steady Based on the above conditions, what equipment is affected and what procedures are required?

A. Core Spray system 1 pumps NOT available, enter Primary Containment Control 8.

~~~~

Core SDrav svstem 2 Dumm NOT available. enter Secondary Containment Control

~

C. Containment Spray system 1 pumps NOT available, enter Primary Containment Control rr Containment Spray system 2 pumps NOT available, enter Secondary Containment ANSWER: IB REFERENCE(S): EOP bases I [ref #2] I [ref #3]

References to be provided EOPs w/o entry conditions [ref prv #2]

during exam:

Question Source Bank I Modified Bank 1 [XI 1 New Question Cognitive Level: Memory or Fundamental I I

[XI Comprehension or

Knowledge and Ability Reference Information RO SRO 209001 Low Pressure Core Spray G 2.1.31 Importance 3.9 Rating What is the status of the EDGs and the Core Spray systems one minute after the above conditions occur?

A. I EDG 1 idlina, EDG 2 fast start, 1A & 1D Mains on, 3D Booster on B. 1 EDG 1 & 2 idlina. 1B 8.1 C Mains on, 38 & 3C Boosters on

~~ ~

C. EDG 1 idle, EDG 2 fast start, 1A & 1B Mains on, 3B Booster on D. EDG 1 & 2 idling, 1A & 1D Mains on, 3D Booster on ANSWER: ID REFERENCE(S): T-2-e I proc. 341 A is incorrect, EDG 2 does not fast start.

B is incorrect, 1B/1C & 3B/3C are on the non-powered bus.

Explanation: C is incorrect, EDG 2 does not fast start.

D is the correct answer, EDGs have idle start signal and 1A/1 D will start on hi dw press and 3D will start because 3A cannot start.

References to be provided None [ref prv #2]

during exam:

Learning 10450 Objective Question Source Bank 1 Modified Bank 1 New [XI Question Cognitive Level: Memory or Fundamental Comprehension or [XI Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I 55.43 1 (b) (2)

Knowledge and Ability Reference Information RO SRO 21 1000 Standby Liquid Control System A2.04 I Importance 3.4 1 1 Rating Ability to (a) predict the impacts of the following on the Standby Liquid Control System system; and (b) based on these predictions, use procedures to Inadequate system flow correct, control, or mitigate the consequences of those malfunctions or oDerations:

Question:

Unit Supervisor orders the URO to initiate liquid poison IAW Support Procedure 22. The URO places the STANDBY LIQUID CONTROL keylock in the FIRE SYS 2 position. The following conditions are observed:

0 PUMP ON light for system 2 illuminated (Panel 4F) 0 PUMP DlSCH PRESS greater than Rx pressure (Panel 4F) 0 Squib continuity meter behind 4F reads 4.2 mA for system 2 0 RWCU system is in service B is the correct answer, Squib valve did NOT fire and FLOW ON and SQUIB VALVE OPEN alarms are not in. Continuity meter shows squib did not fire, SP-22 directs System 1 to be initiated.

C is incorrect, liquid poison is not injecting.

Knowledge and Ability Reference Information RO SRO 218000 Automatic Depressurization G 2.1.28 Importance 3.3 System Rating 0 The reactor is at 8% power MSlVs are shut 0 Reactor pressure is fluctuating between 1045 and 1070 psig 0 Torus temperature is 75 deg. F 0 Torus level is 146 in.

The Automatic Depressurization System is.. .

A. operating as designed, initiate Standby Liquid Control, IAW SP-22 B.

NOT operating as designed, place EMRVs to MAN to stabilize RPV pressure below 1045 psig, IAW RPV Control - w/ATWS NOT operating as designed, open all 5 EMRVs, IAW Emergency Depressurization -

C.

w/ATWS operating as designed, place EMRVs to MAN until RPV pressure is 920 psig, IAW RPV D.

Control - w/ATWS REFERENCE(S): I EOP flowcharts I B-3-g I [ref #3]

I Fluctuating pressure indicates cycling EMRVs.

I A is incorrect, ADS working, but no requirement to inject SLC.

B is incorrect, ADS working and stabilizing pressure is wrong action for Explanation:

cycling EMRVs.

C is incorrect, ADS working, ED not required for these conditions.

D is the correct answer, reduce to 920 psig IAW RPV Control - w/ATWS References to be provided I EOP flowcharts I [ref prv #2]

Learning 10450 0bjective Question Source Bank I Modified Bank I [XI I New Question Cognitive Level: Memory or Fundamental [XI Comprehension or Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I I 55.43 (b) (5)

Knowledge and Ability Reference Information RO SRO 21 2000 RPS A2.06 Importance 4.1 4.2 Rating Ability to (a) predict the impacts of the following on the RPS system; and (b) based on those predictions, use procedures to correct, control, or High Reactor Power mitigate the consequences of those abnormal conditions or operations The plant is at 100% power when annunciator APRM HI HVINOP for RPS channels I & II come in.

The RPS system de-energizes BUT 40 rods remain partially or fully withdrawn with the following conditions:

Reactor power is 45%

0 Reactor level is 160 in. TAF and steady 0 Reactor pressure is 920 psig MSlVs are open SP-16 and 18 have NOT been ordered 0 LPRMs are oscillating at 35 watts/cm2 peak to peak Based upon the above information, and as the Unit Supervisor, your next priority should be to ...

A. I Bwass MSlV 10-10 isolations IAW SP-16 B. Terminate and prevent injection IAW SP-17 C. Bypass RBCCW isolations IAW SP-18 D. Initiate Liquid Poison IAW SP-22 ANSWER: ID 1 -

I I

REFERENCEE): I EOP bases I [ref #2] I [ref #3]

Mitigation of power operations should take precedence over all other actions, since power oscillations of the magnitude could lead to core damage (Large Oscillation Threshold)

Explanation: A is incorrect.

B is incorrect, .

C is incorrect, .

D is correct. ~

References to be provided EOP flow charts w/o entry [ref prv #2]

during exam: conditions Learning 10450 Objective

Question Source Bank I Modified Bank I I New [XI u Question Cognitive Level: Memory or Fundamental Comprehension or [XI Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I 55.43 I (b) (5)

Knowledge and Ability Reference Information RO SRO 201002 Reactor Manual Control System A2.02 Importance 3.3 Rating Ability to (a) predict the impacts of the following on the Reactor Manual Control System system; and (b) based on these predictions, use procedures to Rod drift alarm correct, control, or mitigate the consequences of those malfunctions or oDerations

~~~~

Question:

The plant is operating at 100% Power and the following conditions exist:

ROD DRIFT alarm is received and rod 10-35 moves out to position 48 without operator action 0 All attempts to insert the control rod are unsuccessful 0 Investigation reveals NO known cause for the failure Based on the above conditions, which of the following action is required?

Knowledge and Ability Reference Information RO SRO 24 1000 ReactorRurbine Pressure G2.4.21 Importance 4.3 Regulating System Rating Given the following:

0 The plant is operating at 100% power.

0 The main turbine trips.

0 All Turbine Bypass Valves fail to open.

All other systems function as designed.

Which of the following correctly describes the plant response?

A. Reactor scrammed on high neutron flux B. All EMRVs open and safety valves may open C. Isolation condensers isolate on high steam flow D. The transient causes a violation of the MCPR safety limit REFERENCE(S): I Tech Spec 3.1 I [ref #2] I [ref #3]

I A is incorrect, anticipatory scram B is the correct answer, .

Explanation: C is incorrect, IC will not isolate under these conditions because recirc pumps will trip on hi pressure.

D is incorrect, MCPR should not exceed its limit.

References to be provided None [ref prv #2]

during exam:

Learning 02314 0bjective Question Source Bank I Modified Bank I [XI I New Question Cognitive Level: Memory or Fundamental Comprehension or 1x1 Knowledae Analvsis 10 CFR Part 55 Content: I 55.41 I 55.43 I (b) (1)

Question # I S19 Examination Outline Cross-reference Level I SRO I Tier # I 3 I Group# I 1 Knowledae and Abilitv Reference Information IRO l S R 0 2.1 Conduct of operations 2.1.12 Importance 2.9 4.0 Rating Ability to apply technical specifications for a system 1

~ ~ ~ ~ ~ ~

Question:

Weekly surveillance results on the " B Station Battery are as follows:

0 Overall battery voltage while on Float Charge: 128.5 volts Pilot cell voltage while on Float Charge:

Pilot cell specific gravity (temperature corrected):

You are required to.. .

2.1 5 volts 1.175 9 A. notify Plant Engineering ONLY.

B. Be in COLD SHUTDOWN within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ~ ~ ~

C. Test all battery cells for voltage and specific gravity.

D. Commence an equalizing charge on the " B Station Battery.

T.S. 3.7.A.4; REFERENCE(S): 634.2.002 0P-0c-100 4.7.B.1 .d I A is incorrect readings are out of spec B is correct Explanation:

C is incorrect for weekly surveillances References to be T.S. section 4.7

_p" provided during exam:

Learning 10451 0bjective Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental Comprehension or X Level: Know1edge Analysis

Knowledge and Ability Reference Information RO SRO 2.1 Conduct of operations 2.1.23 I Importance 3.9 4.0 I

I Rating Ability to perform specific system and integrated plant procedures during different modes of plant operation.

Question:

In accordance with HU-AA-101, Human Performance Tools and Verification Practices, which of the following is the correct method to verify the position of a valve that will be throttled?

(1) concurrently A-(2) performer (1) concurrently B.

(2) verifier

c. (2) independently (1) performer (1) independently Dm (2) verifier ANSWER: ID REFERENCE(S) : HU-AA-101 A is incorrect, as the two must independently locate and identify the valve, and the performer does NOT physically touch or point to it prior to manipulation Explanation: B is incorrect, as the two must independently locate and identify the valve C is incorrect, as the performer does NOT physically touch or point to it prior to manipulation D is correct References to be None Learning C&T lesson plan - obj. 24 Objective Question Source Bank I Modified Bank I I New X Question Cognitive Memory or Fundamental X Comprehension or Level: Knowledge Analysis

\J Knowledge and Ability Reference Information RO SRO G 2.2.29 Importance 3.8 Rating A Fuel Assembly is discovered to be mis-located in the core after performing the A.

following fuel move B.

~~~

A Fuel Assemblv is discovered to be mis-located in the spent fuel pool

~

C. The fuel move worksheet is discovered to be in error prior to the next move A Fuel Assembly is discovered to be mis-oriented in the core upon unlatching and raising ANSWER:

REFERENCE(S): Procedure 205 I [ref #2] 1 [ref #3]

A is the correct answer.

B is incorrect,not an error in the fuel pool.

Explanation:

C is incorrect not an error until fuel is moved and placed incorrectly.

I D is incorrect, not an error until bridge is moved north/south..

References to be provided I None I [ref prv #2]

W Learning 1129 Objective Question Source Bank 1 [XI I Modified Bank I I New Question Cognitive Level: Memory or Fundamental I I Comprehension or [XI I Knowledge I Analysis I 10 CFR Part 55 Content: I 55.41 I 55.43 I (b) (7) I

Knowledge and Ability Reference Information RO SRO G 2.2.22 Importance 4.1 Ratina Knowledge of limiting conditions for operations and safety limits.

Question:

Given the following conditions:

0 Reactor is at 100% power 0 MCPR is determined to be 1.08 What action is required IAW Technical Specifications?

A. I The reactor shall be shutdown immediatelv B. The reactor shall be placed in cold shutdown in 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months C. Return MCPR within limits in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be shutdown in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Return MCPR within limits in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in cold shutdown in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ANSWER: [ A REFERENCE(S): T.S. 2.1, sect. 6 I [ref #2] I [ref #3]

A is correct, for any safety limit violation.

B is incorrect, plausible for violation of LCO but not for safety limit.

Explanation: C is incorrect, plausible for violation of steady state LCO, but cold shutdown required.

D is incorrect, plausible for violation of steady state LCO.

. I during exam:

Learning I 10451 Question Source Bank I Modified Bank I [XI I New Question Cognitive Level: Memory or Fundamental Comprehension or [XI Knowledge Analysis (letter) 10 CFR Part 55 Content: 55.41 num 55.43 (b) (2)

Knowledge and Ability Reference Information RO SRO 2.3 Radiation Control 2.3.1 Importance 2.6 3.0 Rating 0 General area radiation of 120 mrem/hour 0 Smearable contamination of 100 d p d l 0 0 cm2beta-gamma Which of the following posting(s) should be applied to this area?

Level: 1 Knowledge I Analysis 4

Knowledge and Ability Reference Information RO SRO G 2.4.38 Importance 4.0 Rating Question:

The plant is at 100% power when the following events occur:

At 0810:

All off-site power is lost The generator trips and the reactor scrams EDG 1 starts and its output breaker closes and supplies power to its respective bus 0 EDG 2 fails to start At 0813:

EDG 2 fails to emergency start from the control room At 0828:

EDG 2 is started locally and it output breaker is closed and it supplies power to its respective bus What is the LATEST time that a classification declaration can be made based on the above conditions IAW EP-OC-111, Emergency Classification and PARS?

A. 0825 B. 0828 C. 0840 D. 0843 15 minutes to declare and then 15 minutes to notify NJSP/OEM. In this case it will take 15 minutes for the classification category to be met [from 0810 to 08251 and then 15 minutes to make the classification.

Explanation:

A is incorrect, this is the time it takes for the conditions to occur.

B is incorrect, not based on emergency start not working.

C is the correct answer, this is the time limit to declare the event.

1 D is incorrect, over the limit but would fit 15 min. from the 0828 time.

References to be provided I EP-OC-1010 I [ref Drv #21 Learning 08908 3bjective

Question Source Bank I Modified Bank I 1 New [XI

.-.-, Question Cognitive Level: Memory or Fundamental Comprehension or 1x1 Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I I I 55.43 (b) (5)

Knowledge and Ability Reference Information RO SRO G 2.4.16 Importance 3.0 4.0 Rating 0 Torus Pressure is 32 psig and rising slowly 0 Torus Level is 468" H2 Concentration is 1.7%

0. CHRRMS reads 2,000 WHr 0 All control rods are fully inserted What action is required?

~~ __

A. Vent the Torus through V-28-1K A W SP-32.

B. Vent the Drywell through V-23-21, V-23-22 IAW SP-33.

C. Vent the Drywell through V-27-3, V-27-4 IAW SP-34.

D. Vent the Drywell through V-23-13, V-23-14 IAW SP-36.

ANSWER: (c REFERENCE(S): Primary Containment Control I [ref #2] I [ref #3]

Explanation:

B is incorrect; but would be correct for level between 348 and 461 in.

C is correct References to be provided EOP flow charts wlo entry [ref prv #2]

during exam: conditions Learning 10450 0 bjective Question Source Bank . I I Modified Bank I [XI New Question Cognitive Level: Memory'or Fundamental Comprehension or 1x1 Knowledge AnaIysi s 10 CFR Part 55 Content: I 55.41 I I 55.43 (b)(5)

ML050250141

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Subject:

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