ML050270025
| ML050270025 | |
| 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 | |
| Download: ML050270025 (143) | |
Text
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EXAMINATION ANSWER SHEET Oyster Creek NRC ILT 2004 EXAM 69Q 8 0 70Q 8 0 748 8 0 I !!,
-. i. 1.. 1
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List of references for NRC ILT written exam 12-10-2004 Reference Steam Tables 02.1 -2 03-2 TS 3.2 w/o bases TS 3.3 w/o bases TS 3.7 & 4.7 w/o bases TS 3.8 SP-4 SP-28 Radiological Survey Map Power to Flow map APRM/LPRM status sheet Reactivity Control TS Reactor Coolant TS Electrical TS, surveillance Isolation Condenser TS Operation of the Core Spray system Level Instrument Availability 609.4.001 -1 & -2 & acceptance criteria EP-OC-1010 EAL chart 4 main EOP flow charts w/o entry conditions; RPV Control - No ATWS, RPV Control -
With ATWS, Primary Containment Control, Secondary Containment & Radioactivity Release Control
Knowledge and Ability Reference Information 295001 I Partial or Complete LOSS of I AK3.02 I Importance 1 Forced Core Fiow Circulation Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
Question:
B.
C.
D.
Reactor power response rise during the first two minutes of operator action due to the pump discharge valve closing drop during the first two minutes of operator action due to the pump discharge valve closing 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 closing, then return to 75%
~~
Given the following:
ANSWER:
I A REFERENCE(S::
0 0
0 0
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 ABN-2 I [ref #2]
I [ref #3]
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.
Explanation:
Power will...
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.
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 the stopped recirc loop.
References to be None
[ref prv #2]
Learning Objective 10450
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 Content: 1 55.41 1 (b) (5)
I 55.43 I
Knowledge and Ability Reference Information 295003 Partial or Complete Loss of AC AA1.03 Importance Power Rating RO SRO
4.4 Question
The plant has experienced a loss of offsite power, and the following conditions exist:
Ability to operate and/or monitor the following as they apply to Partial or Complete Loss of AC Power:
Buses 1 C 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Systems necessary to aSSure safe plant shutdown.
If a plant cooldown is commenced at the MAXIMUM allowable cooldown rate, what will be the MINIMUM time it takes to clear the shutdown cooling interlocks, assuming a constant cooldown rate?
A. I 1.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> neferences to ~3 B. 12.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> steam tames
[ret prv #zj C. I 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> Learning Objective D. I22 hours 10450 Explanation:
Question Source Bank I Modified Bank I I New Question Cognitive Memory or Fundamental Comprehension or Level:
Knowledge Analysis I
[XI
[XI I
1 ABN-36 J [ref #2]
I [ref Maximum allowable cooldown rate during loss of AC power is 10 deg. F/hr.
Starting temperature @ 935 psig is 538 deg. F SDC interlocks clear 6 350 deg. F Required cooldown of 188 deg. F to clear SDC interlocks.
A. assumes a Tech Spec allowable cooldown rate of 100 deg. F/hr B. assumes the administrative limit of 90 deg. F/hr.
C. is the correct answer.
D. is incorrect, but plausible if a math error is committed.
I -_
I
. I
.. ^.
Knowledge and Ability Reference Information 295004 Partial or Complete Loss of D.C.
AAI.03 Importance Power Rating Power:
Question:
Given the following:
0 The plant is at 100% power The plant is in a normal electrical plant alignment DC Distribution Center C is de-energized due to a fault Troubleshooting actions for DC-C are in progress Ability to operate and/or monitor the following as they apply to Partial or Complete Loss of D.C.
Subsequently, a reactor scram occurs.
AC electrical distribution A.
B.
C.
D.
Explanation:
Buses 1 A and 1 C are de-energized; buses 1 B and 1 D are energized from offsite power.
Bus 1A is de-energized; bus 1 C is energized from #I EDG; buses 1 B and 1 D are energized from offsite power.
Buses 1 B and 1 D are de-energized; buses 1 A and 1C are energized from offsite power.
Bus 1 B is de-energized; bus 1 D is energized from #2 EDG; buses 1A and 1 C are energized from offsite power.
1C buses will be de-energized if breaker 1A is closed (normal lineup for 100% power.)
B. is incorrect. Bus tie breaker 1C will not open, and #1 EDG will not automatically start.
C. is incorrect. Wrong control power source.
D. is incorrect. Wrong control power source.
ANSWER:
] A REFERENCE(S):
ABN-55 I ref#^]
I [ref #3]
References to be provided during exam:
None
[ref prv #2]
Learning 0 bjective 10450,081 53 Question Source Bank I Modified Bank I I New Question Cognitive Memory or Fundamental [XI Comprehension or Level:
Knowledge Analysis
[XI
~~
~
55.41 10 CFR Part55 Content:
(b) (7) 55.43
Knowledge and Ability Reference Information 295005 I Main Turbine Generator Trip I AK1.O1 I Importance I Rating Knowledge of the operational implications of the RO SRO 4.0 following concepts as they apply to Main Turbine Generator Trip:
I Based on the above conditions, reactor power will.,.
Pressure effects on reactor power A.
B.
C.
D.
REFERENCE(S):
rise due to loss of feedwater heating.
rise due to a rise in reactor pressure.
lower due to a drop in reactor pressure.
lower due to an automatic scram.
~~
Explanation:
References to be provided during exam:
I 31 5.1, step I
I None I 3.3.13.3 A. is incorrect, as feedwater heating is not in service below -30% power.
- 6.
is incorrect, steam flow is cutoff, but BPV will open, lowering pressure.
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.)
NOTE: This event occurred during 1 R18 startup and is an LER Learning Objective 1 196,1200 Question Source Bank I Modified Bank I 1 New
[XI Question Cognitive Memory or Fundamental I [XI I Comprehension or Level:
I Knowledge 1 Analysis 10 CFR Part 55 E E A 4 Ik\\ fC\\
E E A?
d J - V l
\\UJ \\JJ J d. T W
Knowledge and Ability Reference Information RO 295006 Scram AK1.03 Importance 3.7 Rating Given the following:
SRO 4.0 0
0 0
0 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 48 on the full core display All other control rods indicate GREEN-GREEN on the full core display Knowledge of the operational implications of the following concepts as they apply to Scram:
Which of the following actions will provide the MAXIMUM dP for successful rod insertion?
Reactivity control A.
B.
C. 1 Close the CRD cooling water Dressure control valve and manually drive the rods Reset the scram and then manually re-scram the reactor.
Place the mode switch to REFUEL and manually drive the rods ANSWER:
I D REFERENCE(S):
Explanation:
SP-21 I [ref #2]
I [ref #3]
~~
A is incorrect, as a full core scram will not develop maximum dP since scram discharge volume will not be vented and charging header pressure will be lower.
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.
References to be provided during exam:
None
[ref prv #2]
Learning 0 b ject ive 10450 Question Source Level:
Question Cognitive Bank I Modified Bank I I New
[XI Memory or Fundamental Comprehension or
[XI Knowledge Analysis 55.41 10 CFR Part 55 Content:
(b) (5) 55.43
V
--i Knowledge and Ability Reference Information 295006 I Scram I AA2.01 I Importance RO SRO 4.5 4.6 Ability to determine and interpret the following as they apply to Scram:
Question:
The reactor is operating at 100% power, when a loss of offsite power occurs.
I Rating I
Reactor power response A.
B.
C.
D.
REFERENCE(S):
initially rise, then immediately drop due to a scram when the turbine stop valves close.
initially rise, then immediately drop due to a scram when the acceleration relay actuates.
immediately drop due to a scram when the turbine stop valves close.
immediately drop due to a scram when the acceleration relay actuates.
Explanation:
UFSAR, section 15.2.2.2 References to be
[ref #3]
[ref #21 provided None during exam:
[ref prv #2]
Learning Objective 10450,01086,10453 Question Source 1 Bank 1 Modified Bank I I New 1 1 1 ase+inn Pnan;tkra I Rflnmnrw n r Fiindamnntal 1 rK1 I Cnmnrmhtanainn nr
[XI U U ~ 3 S I U I I V U y I I I L I v ~
Level:
....VI, V. I U. I Y U... Y.. C U.
L,.,
-w...P.w..w...-..
- w.
Knowledge Analysis l n P C P D a d EC I
55.41 I W VI I I r L I 1 L IclIcl Content:
(b) (5) 55.43
I-Knowledge and Ability Reference Information RO 29501 6 Control Room Abandonment AA2.02 Importance 4.2 Rating SRO 4.3 0
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 Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT:
Based on the above conditions, RPV water level indication is available at the Remote Shutdown Panel AND at...
Reactor water level A. I RKOI and RK02 B. IRK02 and RK03 level can be read from the triple low Barton instruments as well.
B is incorrect, as it does not address the triple low Barton on RKOI and RK03 has no RPV water level instrumentation on it..
Knowledge and Ability Reference Information 29501 8 Partial or Complete Loss of AK1.O1 Importance Component Cooling Water.
3.6 Question
Knowledge of the operational implications of the following concepts as they apply to partial or complete loss of component cooling water:
The plant is operating at 100% power when a leak in the RBCCW system occurs. The leak is determined to be on the common discharge header, and RBCCW surge tank level is constant.
Effects on component/system operations A.
- 6.
C.
Isolate the RWCU system to reduce heat loads.
Start the standby RBCCW pump.
Commence a plant shutdown IAW Procedure 203.
Explanation:
ANSWER:
I C R E F E R ENC E( S) :
A. is incorrect, would be correct for reduced cooling capability, not for a leak.
B. is incorrect, would be correct for a pump trip, not for a leak.
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 ABN-19 I [ref #2]
I [ref #3]
References to be provided during exam:
NONE
[ref prv #2]
Question Source Level:
Question Cognitive Bank I Modified Bank I I New
[XI Knowledge Analysis Memory or Fundamental Comprehension or 1x1 55.41 10 CFR Part 55 Content:
(b) (4) 55.43
Knowledge and Ability Reference Information RO 29501 9 I Partial or Complete Loss of 1 G2.1.30 1 Importance 3.9 SRO 3.4 Ability to locate and operate components, including local controls Conduct of Operations A.
B.
C.
Question:
Given the following conditions:
Manually close Charging Header Isolation V-15-52 Manually close CRD Flow Control Valves NC-30 A/B Manuallv close CRD BvDass Isolation Valve V-15-30 0
The plant has experienced a total loss of Instrument Air 0
The reactor was scrammed successfully 0
RPV water level is 175 in. TAF and slowly rising 0
All feedwater pumps are secured 0
A CRD pump is operating ANSWER:
/ A REFERENCE(S!:
What actions are required to stabilize reactor water level?
ABN-1 I [ref #2]
I [ref #3]
References to be None
[ref prv #2]
Learning 0 bject ive 10450 Question Source Bank I Modified Bank 1 I New Level:
Knowledge Analysis Question Cognitive Memory or Fundamental Comprehension or
[XI
[XI
Knowledge and Ability Reference Information 295021 Loss of Shutdown Cooling G2.4.48 Importance Rating 0
The plant is shutdown 0
0 0
Shutdown cooling is in service with A and B SDC loops in service C SDC loop is filled and vented, and has 1500 gpm RBCCW flow through its HX RPV temperature is 310 deg. F and being cooled down at 10 deg. F per hour with SDC The temperature switch for the A SDC inlet water temperature fails to 390 degrees F due to a fault RO SRO 3.5 3.8 What effect does this failure have on the SDC system, and what actions should be taken in A.
B.
response to this failure?
I V-17-19 and V-17-54 (SDC Inlet and Outlet Isolation Valves) will close and the SDC system will isolate. The faulty temperature switch must be overridden in order to recover SDC.
V-17-19 and V-17-54 (SDC Inlet and Outlet Isolation Valves) will close and the SDC system will isolate. Alternate means of core cooling must be employed.
V-17-19 (SDC Inlet Isolation Valve) will close and A and B SDC pumps will trip.
Alternate means of core cooling must be employed V-17-19 and V-17-54 (SDC Inlet and Outlet Isolation Valves) will remain open and the A SDC pump will trip. Continue cooldown with B and C SDC pumps Proc. 305 C-2-d REFERENCE(S):
RAP Explanation:
[ref #3]
References to I
..I..
I I
When SDC loop suction temperature exceeds 350 degrees, this causes the respective SDC pump to trip. System does not isolate. If RCP loop temperatures exceed 350 degrees, this will cause the SDC system to isolate. Therefore; A is incorrect for this situation, but would be correct for a recirc pump suction temperature switch fault.
6 is incorrect, but would be correct for a recirc pump suction temperature switch fault.
C is incorrect but is correct sequence if inlet isolation valve were to close.
D is correct.
I None 1 [refprv#2]
0 bject ive
'L, Question Source Bank I Modified Bank I I New Level:
Knowledae Analvsis Question Cognitive Memory or Fundamental Comprehension or
[XI
[XI
---e-i_c-Knowledge and Ability Reference Information 295023 Refueling Accidents AA2.01 Importance Rating RO SRO 3.6
4.0 Question
Given the following conditions:
Ability to determine and/or interpret the following as they apply to REFUELING ACCl DENTS:
0 0
0 The plant is in a refueling outage Reactor Building Ventilation Exhaust radiation monitors are both reading 2 mr/hr 69 and C9 radiation monitors are both reading 3 mr/hr A fuel bundle is dropped from the grapple as it is being moved Area radiation levels At time T = 5 minutes, B9 radiation monitor reads 55 mr/hr At time T = 6 minutes, Reactor Building Ventilation Exhaust channel A-1 reads 10 mr/hr At time T = 7 minutes, Reactor Building Ventilation Exhaust channel A-2 reads 11 mr/hr At time T = 8 minutes, C9 radiation monitor reads 60 mr/hr A.
B.
C.
D.
T = 5 minutes T = 6 minutes T = 7 minutes T = 8 minutes Explanation:
References to I a 2-minute timer, which will then cause a RBHVAC isolation at the end of that 2-minute period. The RB Vent. Exhaust rad monitors alarm at 9 mr/hr.
When either of these alarm, it causes an immediate RBHVAC isolation.
Additionally, it takes one-out-of-two taken ONCE logic. Therefore:
A is incorrect, as no time delay is factored in B is correct C is incorrect, as the RBHVAC is already isolated and it does not take both B9 and C9 monitors to isolate D is incorrect, as the RBHVAC is already isolated and it does not take both RB Vent. Exhaust monitors to isolate 3
I None provided during exam:
I Learning I01129
.d Question Source Bank I Modified Bank I I New X
Question Cognitive Memory or Fundamental I I Comprehension or X
Knowledge and Ability Reference Information RO 295024 High Drywell Pressure EA1.06 Importance 3.7 Rating 0
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 SRO 3.7 What effect does this have on the plant?
A. I NZOl B and NZ03B start, NZOl A and NZ03A do NOT start, both EDGs idle start Ability to operate and/or monitor the following as they apply to HIGH DRYVVELL PRESSURE:
Emergency Generators B.
C.
D.
NZOl B and NZ03B start, ONLY #2 EDG idle starts NZOl A&B start, NZ03A&B start, both EDGs idle start NZOlA&B start, NZ03A&B start, ONLY #2 EDG idle starts ANSWER:
I C REFERENCE(S):
341, B-1-e I [ref #2]
I [ref #3]
Explanation:
A is incorrect as both core spray systems start B is incorrect as both core spray systems and both EDGs start.
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 None during exam:
[ref prv #2]
Learning 0 bjective 00788 Question Source Bank I Modified Bank I I New Question Cognitive Memory or Fundamental [XI Comprehension or Level:
Knowledge Analysis
[XI 55.41 10 CFR Part 55 Content:
(b) (7) 55.43
Question # I 13 Examination Outline Cross-reference Level I RO I Tier #
I 1 I Group# I 1 Knowledge and Ability Reference Information 295025 I High Reactor Pressure I EA1.07 I Importance RO SRO 4.1 4.1 Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE:
Given the following:
ARI/RPT/ATWS (Plant Specific) 0 0
MSlVs inadvertently close 0
The plant is at 45% power and stable 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 NO other operator actions are taken A.
B.
yr 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 ARI actuation complete loss of recirculation flow, and will ultimately reach the source range because of ARI actuation partial loss of recirculation flow, and will remain at that lowered power level, ultimately CI.
requiring an Emergency Depressurization due to exceeding the-HCTL complete loss of recirculation flow, and will remain at that lowered power level, ultimately
- u.
1 requiring an Emergency Depressurization due to exceeding the HCTL ANSWER:
IC References to be provided during exam:
None
[ref prv #2]
10 CFR Part 55 Content:
Learning Objective 1
55.41 I (b) (6) 1 55.43 1 00208,00209 Question Source Level:
Question Cognitive Bank I Modified Bank I I New
[XI Knowledge Analysis Memory or Fundamental Comprehension or
[XI
Knowledge and Ability Reference Information 295026 Suppression Pool High Water G 2.1.25 Importance TemDerature Ratina RO SRO 2.8 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain Derformance data.
A.
B.
C.
Question:
190deg. F 193deg. F 200dea. F Given the following conditions:
References to be 0
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 Core Spray pumps NZOl A and NZOI B are operating at 4,000 gpm each Torus water level is 150 inches and stable Containment Spray pump 51 A is running in Torus Cooling mode at 4,500 gpm Containment Spray pump 51 C is running in Drywell Spray mode at 4,500 gpm SP-4
[ref prv #2]
What is the HIGHEST Torus temperature that is allowed without exceeding any Core Spray limits?
Learning 0 bjective 03023 D. I 202 deg. F ANSWER:
I B REFERENCE(S I SP4 I [ref #2]
I [ref #3]
For the conditions stated, CS static head adiustment is 2.1 wig.
Explanation:
For 12 psig - I static head adjustment.
For 4 psig - G static head adjustment.
Use 4 psig and static head of 2.1 and NZOl C NOT running curve to determine 193 deg. F is the highest temp. Therefore:
A is incorrect as it is using the NZOlC curve.
B is correct.
C is incorrect as it is using 12 psig and the NZOl C curve
L Question Source Bank I Modified Bank I 1 New
[XI Question Cognitive Memory or Fundamental I 1 Comprehension or
[XI Level:
I Knowledge I Analysis
Knowledge and Ability Reference Information 295028 High Drywell Temperature EA2.03 Importance Rating Question:
Given the following:
RO SRO 3.7 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 A Yarway 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 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE:
Reactor water level D. I cannot be determined A.
B.
C.
ANSWER:
IC I
is 90 in. TAF is 92 in. TAF is 170 in. TAF REFERENCE(S):
[ SP-28 I [ref #2]
I [ref #3]
I All instruments are below RPV saturation messure, therefore:
Explanation:
A is incorrect as it is below minimum usable indicating level 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 provided during exam:
c SP-28
[ref prv #2]
Learning Objective 10445 Question Source Question Cognitive Bank I Modified Bank I I New
[XI Memory or Fundamental I I Comprehension or Wl Level:
I Knowledge I Analysis
Knowledge and Ability Reference Information RO 295030 Low Suppression Pool Water EK2.08 Importance 3.5 Level Rating The plant is operating at 100% and stable 0
The TORUS LEVEL HVLO alarm annunciates 0
The STA informs you that torus water level is low, and dropping at 2 inches per minute SRO 3.8 Assuming the time starts when the Torus low level alarm is received and assuming a constant rate of torus level drop, answer the following two questions.
Knowledge of the interrelations between LOW SUPPRESSION POOL WATER LEVEL and the following:
- 1.
- 2.
What is the MAXIMUM time before EMRVs can NO LONGER be manually opened?
What is the basis for this requirement?
EMRV discharge submergence A.
B.
D.
Explanation:
Approximately 16 to 17 minutes, due to loss of suppression capability when EMRVs are open.
Approximately 16 to 17 minutes, due to loss of suppression capability for a LOCA.
Approximately 26 to 27 minutes, due to loss of suppression capability when EMRVs are open.
Approximately 26 to 27 minutes, due to loss of suppression capability for a LOCA.
Containment Control. Candidates are required to know this fact.
At 2 in/min drop, it has to go from 143 to go, or -53/2 or 26.5 minutes.
At 110 inches, torus downcomers are uncovered. At 90 inches, EMRV Y quenchers are uncovered. Even though the EOPs require ED before reaching 110 inches, it is appropriate to ED even if Torus level is below 110 inches. However, EMRVs can not be opened if Torus level is less than 90 inches when ED is commenced. Therefore:
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 D is incorrect due to wrong basis applied.
ANSWER:
I C REFERENCE(S):
RPV Control - No EOP Users Guide ATWS References to be None
Question Source Question Cognitive Bank I Modified Bank I I New
[XI Memory or Fundamental I I Comprehension or
[XI Level:
I Knowledge I Analysis
Knowledge and Ability Reference Information 295031 Reactor Low Water Level EK3.05 Importance Rating 0
0 0
0 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 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 RO SRO 4.2 4.3 Based upon the above information, which of the following is correct and why?
Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL:
Emergency depressurization Explanation:
Bm cm Dm References to I Maintain present conditions and continue trying to restore additional injection systems, because adequate steam flow exists to keep the core less than 1500 deg. F.
Maintain present conditions and continue trying to restore additional injection systems, because adequate steam flow exists to keep the core less than 1800 deg. F.
Conduct an Emergency Depressurization because insufficient steam flow exists to keep the core less than 1500 deg. F.
Conduct an Emergency Depressurization because insufficient steam flow exists to keep the core less than 1800 deg. F.
REFERENCE(S):
provided during exam:
Learning I 10450 EOP Users Steam Cooling EOP I Guide I
huestion Source Bank I Modified Bank I I New X
Question Cognitive Memory or Fundamental I I Comprehension or X
Knowledge and Ability Reference Information 295037 SCRAM condition present and EK2.10 Importance Reactor Power above APRM Rating Downscale or Unknown Reactor pressure RO SRO
3.8 following
Question:
The plant is at 100% power when the following occurs:
A.
- 6.
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 Control rods are being manually inserted IAW SP-21 When liquid poison tank is at 650 gallons When power reaches IRM range 4, and is continuing to lower Based upon these conditions, when can a plant cooldown be commenced?
ANSWER:
I B REFERENCE(S!:
EOPs I [ref #2]
I [ref #3]
C. I Immediately. since power is within the capacity of the turbine bypass valves Explanation:
A is incorrect because there is no need to inject boron under these conditions.
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%
Learning 0 b ject ive 10450,02257
Question Source Bank I Modified Bank I I New
[XI Level:
Knowledge Analysis Question Cognitive Memory or Fundamental Comprehension or
[XI 10 CFR Part 55 Content: I 55.41 I (b) (10)
I 55.43 1
Knowledge and Ability Reference Information RO 295038 High Off Site Release Rate EK2.07 Importance 3.5 Rating SRO Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following:
Question:
Given the following conditions:
Control Room ventilation The plant is operating at 100% power and steady Annunciator 1OF-1 -d, STACK EFFLUENT HI-HI alarms Stack RAGEMS Channel 1 & 2 are reading above their HI-HI alarm setpoint C.
D.
Which of the following correctly describes the REQUIRED Control Room HVAC System lineup for these conditions?
Partial Recirculation Mode Full Recirculation Mode A. I Normal Mode References to be B. I Purae Mode None
[ref prv #2]
Learning Objective Explanation:
02324 I
I OC Control Room HVAC systems are manually controlled only. No automatic changes to system lineups.
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 remove smoke, fumes or odors from the atmosphere.
C is correct in accordance with actions taken IAW procedure 331.l.
D is incorrect as full recirc mode prevents toxic gas from entering the control room.
Question Source Level:
Question Cognitive Bank I Modified Bank I I New
[XI Knowledge Analysis Memory or Fundamental Comprehension or
[XI
Knowledge and Ability Reference Information 600000 Plant Fire On Site AA1.09 Importance Rating 0
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:
2 detectors in Zone 1 for System A 3 detectors in Zone 2 for System 6 1 detector in Zone 1 for System C 2 detectors in Zone 2 for System C RO SRO 2.5 Which of the following Control Room Halon system(s) will actuate?
Ability to operate and/or monitor the following as they apply to PLANT FIRE ON SITE:
D. System A, 6 and C Plant fire zone panel, including detector location E. System A and B ONLY ANSWER:
I D REFERENCE(S::
F. System B and C ONLY ABN-29 I [ref #2]
I [ref #3]
D. System C ONLY Explanation:
A. 1 System A, B and C 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 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
- 6. I System A and 6 ONLY References to be C. 1 System B and C ONLY None
[ref prv #2]
Learning Objective 10445,10450 Question Source I Bank I Modified Bank I I New I [XI Question Cognitive Level:
Memory or Fundamental Comprehension or
[XI Knowledge Analysis
Knowledge and Ability Reference Information 295008 High Reactor Water Level AA2.02 Importance Rating 0
0 0
0 0
6 EMRV fails open 0
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 Ibdhr Indicated feed flow is 7.1 6 E6 Ibdhr NO operator actions are taken RO SRO 3.4 3.4 Once the plant stabilizes, RPV water level will be the steam flow/feed flow mismatch will be (2) pre-transient conditions.
(1 1 AND Ability to determine and/or interpret the following as they apply to HIGH REACTOR WATER LEVEL:
Steam flow/feed flow mismatch Explanation:
A.
=.
c-Dm References to I (1) above 160 in. TAF (2) less than (1) below 160 in. TAF (2) less than (1) above160 in. TAF (2) greater than (1 )
below 160 in. TAF (2) grei 1
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 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 Learn i n g Objective D is correct
?
I None 10450
-./
Question Source Bank I Modified Bank 1 1 New X
Question Cognitive Memory or Fundamental Comprehension or X
10 CFR Part 55 Content: I 55.41 I (b) (5) 1 55.43 I Level:
Knowledge Analysis
-4 Knowledge and Ability Reference Information 295007 High Reactor Pressure G2.1.23 Importance Rating RO SRO 3.9 4.0 0
0 0
0 MSlVs close on high Trunnion Room temperature All rods remain at their pre-transient positions RPV pressure is 121 5 psig and steady Drywell pressure is 17 psig and rising All other systems operated as expected A
B C
D placing BOTH ICs in service, IAW SP-11 terminating and preventing injection, IAW SP-17 reopening MSIVs, IAW RPV Control -with ATWS manually opening ALL EMRVs, IAW Emergency Depressurization REFERENCE(S):
References to be txovided durina exam:
1 :;:trol I EOP User's Guide 1 [ref #3]
EOPs without entry conditions Question Source Question Cognitive Level:
I 02257 Learning Obiective Bank I Modified Bank I I New
[XI Memory or Fundamental
[XI Comprehension or Knowledge Analysis
Knowledge and Ability Reference Information 29501 0 High Drywell Pressure AKl.03 Importance Rating Given the following:
RO SRO 3.2 3.4 A high drywell pressure condition is in progress Drywell pressure is 1.8 psig and rising slowly Bulk drywell temperature is 140 deg. F and rising slowly Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE:
Given the above condition, which of the following is NOT an allowable mitigation strategy to lower Drywell temperature?
Temperature increases A.
B.
Reduce RBCCW loads.
Start all drvwell coolina fans.
C.
D.
B is addressed in C-3-f C is addressed in C-3-f Explanation:
~~~~
~~~
~~~
~~~~~~~
~
Start the second RBCCW pump.
Bypass RBCCW isolations and maximize drywell cooling.
I D is an EOP action, and EOPs would not be applicable in this condition References to be I None ANSWER:
I D REFERENCE(S):
RAP C-3-f I C-8-h Learning 0 bjective 00446 Question Source I Bank I Modified Bank 1 I New 1 [XI Question Cognitive Level:
Memory or Fundamental [XI Comprehension or Knowledge Analysis
Question I
I Question:
Given the following:
Knowledge and Ability Reference Information 29501 3 High Suppression Pool AK2.01 Importance Temperature Rating 0
0 Reactor power is 4%
0 0
0 A plant startup following a refueling outage is in progress RPV pressure is 1020 psig EMRV testing is in progress Torus cooling is in operation Average torus temperature is rising RO SRO 3.6 3.7 Knowledge and Ability Reference Information ANSWER:
I A I Tech I R O l S R 0 Knowledge of the interrelations between HIGH SUPPRESSION POOL TEMPERATURE and Suppression pool cooling A-B.
/5 (1) 105 (2) 110 (1) 110 (2) 120 (1) 95 REFERENCE(S):
Specs 3.5.A.1.c Explanation:
A is correct.
B is incorrect. Scram is at 1 10 and RPV depressurization at 120.
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 Drovided durina exam:
None Learning Objective 10450
d I 10 CFR Part 55 Content: I 55.41 I (b) (3)
I 55.43 I
~
Question Source Bank I Modified Bank 1 I New
[XI Question Cognitive Memory or Fundamental [XI Comprehension or Level:
Knowledae Analvsis
Knowledge and Ability Reference Information 295022 Loss of CRD Pumps AK3.01 Importance Rating Question :
RO SRO 3.7 3.9 Given the following:
Knowledge of the reasons for the following responses as they apply to LOSS OF CRD PUMPS:
A plant startup is in progress RPV pressure is 800 psig The A CRD pump trips on overload and CANNOT be restarted The B CRD pump will not start Reactor Scram A scram is required (1) and rod scram times will be (2) allowable limits A-B-
c-(1) immediately (2) within (1 )
immediately (2) greater than (1)
(2) within when the second accumulator alarms Dm H-7-c RAP REFERENCE(S):
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 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 (1 )
(2) greater than when the second accumulator alarms Explanation:
References to be None Learning Objective 10450
Question Source Bank I Modified Bank I I New
[XI Level:
Knowledge Analysis Question Cognitive Memory or Fundamental Comprehension or
[XI 10 CFR Part 55 Content: I 55.41 I (b) (1 0)
I 55.43 I
Knowledge and Ability Reference Information 295029 High Suppression Pool Water EK3.01 Importance Level Rating The plant has experienced a small LOCA The reactor has been scrammed Drywell pressure is being maintained between 4 and 12 psig with drywell sprays RPV pressure is steady at 800 psig RPV level is being maintained between 138 and 175 in. with Condensate/Feedwater and CRD Torus level is 180 inches and rising at approximately 1 in. every 3 minutes The US has ordered Emergency Depressurization RO SRO 3.5 What is the basis for this decision?
Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL WATER LEVEL:
A. I To prevent exceeding the PCPL if the LOCA were to progress to a DBA LOCA.
Emergency depressurization B. I To prevent exceeding allowable stresses on the EMRV Y wenchers and supports.
References to be C. I To lower pressure as necessaw to allow the low pressure iniection svstems to iniect.
EOPs without entry conditions D. I To prevent possible torus structural damage due to the elevated water level.
ANSWER:
I B REFERENCE(S):
I L L curve EOP bases A is incorrect. If torus level cannot be maintained in the PSP and a vessel Learning Objective Explanation:
03000 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 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
'v Question Source Bank 1 Modified Bank I I New
[XI Question Cognitive Memory or Fundamental [XI Comprehension or Level:
Knowledge Analysis 10 CFR Part 55 Content: I 55.41 I (b) (1 0)
I 55.43 I
Knowledge and Ability Reference Information RO 295009 Low Reactor Water Level AA1.02 Importance 4.0 Rating 0
Plant is at power 0
0 3 feed pumps operating 0
0 0
B feed pump trips Feed flow is 5.5 E6 Ibdhr Reactor level control is in AUTO Master feedwater level setpoint is 160 in.
SRO 4.0 With NO operator action, feed flow will be...
Ability to operate and/or monitor the following as they apply to Low Reactor Water Level:
Reactor water level control A.
B.
C.
5.5 E6 Ibm/hr 5.34 E6 Ibm/hr 4.8 E6 Ibm/hr ANSWER:
I B REFERENCE(S):
J-8-c References to be None Question Source Bank I Modified Bank I I New Question Cognitive Memory or Fundamental 1 [XI I Comprehension or
[XI Level:
I Knowledge I Analysis
--:~
Knowledge and Ability Reference Information RO 205000 Shutdown Cooling K4.01 Importance 3.7 Rating SRO Shutdown cooling is in operation with "A "Shutdown Cooling (SDC) Pump running "E" Recirculation Loop is in service; all other loops are idle The "C" recirc loop temperature instrument fails upscale Knowledge of the Shutdown Cooling system design features(s) and/or interlocks which provide for the following:
Based on the above conditions, which one of the following will occur?
A.
B.
SDC system will isolate on low suction pressure AND running SDC pumps will trip on high temperature Running SDC pumps will trip on low suction pressure AND SDC system will isolate on low suction pressure SDC system will isolate on high temperature AND running SDC pumps will trip on High temperature isolation
- b.
isolation valve closure Running SDC pumps will trip on high temperature AND SDC system will isolate on high ANSWER:
IC REFERENCE(S):
Proc. 305, C-2-d I [ref #2]
I [ref #3]
A is incorrect, system isolates on high temp, pumps will trip on isolation valve closure.
Explanation:
References to be provided during exam:
None
[ref prv #2]
~
~
Question Source Question Cognitive Level:
~
~~
Bank I Modified Bank I I New
[XI Memory or Fundamental [XI Comprehension or Knowledge Analysis 55.41 10 CFR Part 55 Content :
(b) (7) 55.43
Question #
129 Knowledge and Ability Reference Information 207000 Isolation Condenser K1.03 Importance Rating RO SRO 3.7 Knowledge of the physical connections and/or cause-eff ect relationships between ISOLATION CONDENSER and the following:
REFERENCE(S Reactor water level Explanation:
A.
B.
C.
D.
References to I 160 in., to prevent water hammer of the piping.
160 in., to prevent automatic isolation.
180 in., to prevent water hammer of the piping.
180 in., to prevent automatic isolation.
I EOPs I Support Procedure 11 1 A is incorrect, as this is the basis for not initiating ICs above 160 inches, not Learning Objective for isolating them.
B is incorrect, as the level pertains to initiation, and the high flow isolation deals with recirc pumps NE running if ICs are initiated.
C is correct D is incorrect, as the isolation on high flow precaution is to ensure recirc DumDs NE are secured Drior to initiation.
02338 3
I None I
Question Source Question Cognitive Bank I Modified Bank I I New
[XI Memory or Fundamental I [XI I Comprehension or Level:
I Knowledge I Analysis
'v
=----
Knowledge and Ability Reference Information 209001 Low Pressure Core Spray K2.03 Importance System Rating RO SRO 2.9 3.1 Knowledge of electrical power supplies to the following:
Question:
Given the following:
logic 0
0 125 VDC Panel DC-D is deenergized due to a panel fault Two (2) minutes later, drywell pressure rises to 3.6 psig A.
B.
c-Based upon these conditions, Isolation Condenser Core Spray pumps (2) will start.
(1 1 will isolate AND (1)
A (1)
B (1)
A (2)
(2)
(2)
NZOl B and NZOl C NZOl B and NZOl C NZOl A and NZOl B References to be D. 1 [:;
NZC None ANSWER:
I (
REFERENCE(S Learn i n g 0 bjective Explanation:
02030,00302 A and NZOl B I
I RAP 9XF-3-d I RAP B-7-e A loss of DC-D will cause the A Isolation Condenser to automatically isolate on a false high steam/condensate flow signal due to loss of power t6 the isolation logic. However, core spray initiation logic is provided from both DC-D and DC-F. Core spray system I pumps (NZO1 NC) initiation logic is normally from DC-D with a redundant logic circuit from DC-F. Core spray system II pumps (NZO1 B/D) initiation logic is normally from DC-F with a 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 (NZO1 C) will not start.
B is incorrect, as the wrong IC isolation is given, and NZOl C will not start.
C is correct D is incorrect, as the wrong IC isolation is given.
c
i Question Source Bank I Modified Bank I I New X
Question Cognitive Memory or Fundamental Comprehension or X
10 CFR Part 55 Content: I 55.41 I (b) (7)
I 55.43 I Level:
Knowledge Analysis
Question #
I31 I
Knowledge and Ability Reference Information 21 1000 Standby Liquid Control System K6.03 Importance Rating RO SRO 3.2
3.3 Question
Which of the following 460V MCCs MUST have power in order to inject with SLC System l?
Knowledge of the effect that a loss or malfunction of the following will have on the STANDBY LIQUID CONTROL SYSTEM:
A.
1A21 A.C Power B.
1A21A ANSWER:
I A REFERENCE(S):
C.
1 A22 ABN-45, att. 5 D.
1 A23 Explanation:
A. I 1A21 A is correct, as the SLC pump 1A and its squib are powered from 1A21, and SLC pump 1 B and its squib are powered from 1 B21.
B is incorrect, as 1A21A and 1 B21A power Recirc Pump and Core Spray valves ONLY.
C is incorrect, as 1A22 and 1 B22 power Old Radwaste equipment ONLY.
D is incorrect, as 1A23 and 1 B23 power Reactor Building and Office Building fans ONLY.
B. I 1A21A Learn i ng 0 bjective C.
1 1A22 10436 Question Source Question Cognitive Bank I Modified Bank I I New X
Memory or Fundamental I X I Comprehension or Level:
I Knowledge I Analysis
Knowledge and Ability Reference Information RO 21 2000 Reactor Protection System A3.06 Importance 4.2 Rating 3ased upon this, the reactor will (1 )
, and
- he turbine valve response will be (2)
SRO 4.2 A.
hrbility to monitor automatic operation of the
?EACTOR PROTECTION SYSTEM including:
B.
Main turbine trip: Plant-Specific C.
D.
AN RE -
(1)
SCRAM (2)
Turbine Control Valves CLOSED Intercept Valves CLOSED Bypass Valves All open initially; throttle closed to control Reheat Stop Valves OPEN reactor pressure (1)
NOTSCRAM (2)
Turbine Control Valves OPEN Intercept Valves OPEN Reheat Stop Valves OPEN Bypass Valves CLOSED (2)
Turbine Control Valves CLOSED Intercept Valves CLOSED Reheat Stop Valves CLOSED Bypass Valves All open initially; throttle closed to control (1)
SCRAM reactor pressure (1)
NOTSCRAM (2)
Turbine Control Valves OPEN Intercept Valves OPEN Reheat Stop Valves CLOSED ERENCE(S Explanation:
5s Valves CLOSED I
I ABN-10 I RAP P-1-a One MS HI-HI level switch actuation will cause a turbine trip. Any turbine trip from 40% power and above will actuate an anticipatory scram.
Therefore:
A is incorrect, as the reheat stop valves also close on turbine trip 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 I Learning I 01 187 I
Question Source Question Cognitive Bank I Modified Bank I 1 New X
Memory or Fundamental I X I Comprehension or Level:
I Knowledge I Analysis
Knowledge and Ability Reference Information RO 21 5003 Intermediate Range Monitor K6.06 Importance 3.2 (IRM) System Rating
-~
~
Given the following:
SRO 3.4 0
0 0
0 A plant startup is in progress All IRMs are in Range 10 The mode switch has just been taken to RUN IRM 13 takes a step change to 40%
Before IRM 13 can be bypassed, LPRM string 12-1 7 fails to " 0 as indicated on all four (4) LPRM channels Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM:
Besides the APRM DOWNSCALE alarm, which of the following will be received?
APRM A.
B.
C.
D. I LPRM DOWNSCALE. IRM HI-HI, ROD BLOCK alarms, and CHANNEL I half scram.
LPRM DOWNSCALE alarm ONLY.
LPRM DOWNSCALE and ROD BLOCK alarms ONLY.
LPRM DOWNSCALE, IRM HI-HI, and ROD BLOCK alarms ONLY.
Explanation:
References to 12 provided during exam:
I I 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.
Therefore:
A is incorrect, as it is only one of four things that occur.
E3 is incorrect, as it is only two of four things that occur.
C is incorrect, as it is only three of four things that occur. 03-2 LPRM and APRM status information Learning 1 10441
-\\--
Question Source Bank I Modified Bank I 1 New X
Question Cognitive Memory or Fundamental Comprehension or X
10 CFR Part 55 Content: I 55.41 I (b) (6)
I 55.43 I Level:
Knowledge Analysis
Knowledge and Ability Reference Information 21 5004 Source Range Monitoring System K3.02 Importance Rating 1 Reactor manual control: Plant Specific malfunction of the SOURCE RANGE MONITORING SYSTEM will have on the RO SRO 3.4
3.4 following
Question:
Given the following conditions:
Explanation:
IRMs in range 1 Rx mode switch in "Startup" IRMs and SRMs are full in A is incorrect, would be true if not in range 1.
B is incorrect. would be true if mode switch in RUN.
C is incorrect, would be true if detector not full in D is correct, Which of the following will produce a rod block?
References to be A. I I RM 14 indicates 3 on 125 scale None B. 1 APRM 7 indicates 1 on 150 scale.
Question Source Question Cognitive Level:
C. I SRM 24 indicates 100 CDS Bank 1 Modified Bank I 1 New
[XI Memory or Fundamental [XI Comprehension or Knowledge Analysis
Knowledge and Ability Reference Information 21 5004 Source Range Monitoring System Al.01 Importance Ratina Ability to predict and/or monitor changes in I
RO SRO 3.0 3.1 parameters associated with operating the SOURCE RANGE A.
B.
c*
Dm I Detector position (1)
(2) become longer (1)
(2) become shorter (1)
(2) become longer (1)
(2) become shorter all SRMs are greater than 1 E5 cps all SRMs are greater than 1 E5 cps three IRMs in each RPS system read 50% on range 1 three IRMs in each RPS system read 50% on range 1 MONITORING SYSTEM controls including:
Question:
During startup, when the reactor is critical, SRM detectors are initially withdrawn when (1 1 and SRM period will (2) as the detectors INITIALLY start moving References to be None REFERENCE(S Explanation:
Learning Objective I RAP H-7-a I [see question #34]
I procedure 201 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 high flux area.
A. is incorrect, detector withdrawal is dictated by IRM indication and period will initially go shorter B. is incorrect, detector withdrawal is dictated by IRM indication C. is incorrect, as period will initially become shorter D is correct 10444 Question Source Level:
Question Cognitive Bank I Modified Bank I I New
[XI Knowledge Analysis Memory or Fundamental Comprehension or
[XI
Knowledge and Ability Reference Information RO 21 5005 Average Power Range Al.03 Importance 3.6 Monitor/Local Power Range Rating Monitor System 0
0 0
A plant startup is in progress The Mode Switch is in RUN Reactor Power drops, causing APRM 1 DOWNSCALE white light to ILLUMINATE SRO 3.6 Ability to predict and/or monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls including:
selected nor driven. This arrangement is unique to BWR 2s. Therefore:
A would be correct for system 2 Explanation:
Control rod block status A.
B.
C.
D.
cannot be driven in EITHER direction.
can be driven in the inward direction ONLY.
can be driven in the outward direction ONLY.
can be driven in the inward AND outward directions.
ANSWER:
I B REFERENCE(S::
RAP H-7-a I [see question #34]
References to be None Learning 0 bjective 10444 Question Source Question Cognitive Level:
Bank I Modified Bank I I New X
Memory or Fundamental Comprehension or X
Knowledge Analysis
Knowledge and Ability Reference Jnformation 2 1 5005 1 Average Power Range A3.07 Importance Rating I Monitor/Local Power Range RO SRO 3.8 3.8 I Monitor System Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOWLOCAL POWER RANGE MONITOR SYSTEM including:
Question:
A-B-
- c.
Dm RPS status (1) 12.0 E4 (2) rod block (1) 12.0 E4 (2) half-scram (1) 13.5 E4 (2) rod block (1) 13.5 E4 (2) half-scram Given the following:
Explanation:
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)
Only 5 of 10 recirc flow transmitters feed the 4F total recirc flow indicator, causing indicated flow to read 80% of initial flow (1 5 x.8 = 12). A 10% or greater flow mismatch will cause the flow comparator rod block. Therefore:
A is correct 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 Learning Objective 1 flow comparator half scram References to be I Power-to-Flow Map, 202.1-2 I 0021 9 Question Source Bank I Modified Bank I I New X
Question Cognitive Memory or Fundamental Comprehension or X
Level:
Knowledae An alvsi s
Knowledge and Ability Reference Information 2 1 8000 Automatic Depressurization K3.02 importance System Rating RO SRO 4.5 4.6 I Ability to rapidly depressurize the reactor rnalfuncti& of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on B
C.
D.
the following:
Question:
Given the following:
initiate but ONLY C and D EMRVs will open.
NOT initiate because it is bypassed.
NOT initiate because d w e l l Dressure is 1.5 psig.
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 Learning Objective The ADS System will...
10357,00379 A. I initiate and ALL 5 EMRVs will 013811.
Explanation:
I 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 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.
References to be 1 None I
---/
Question Source Bank I Modified Bank I 1 New X
Question Cognitive Memory or Fundamental Comprehension or X
10 CFR Part 55 Content: I 55.41 I (b) (7)
I 55.43 I Level:
Knowledge Analysis
Knowledge and Ability Reference Information RO 223002 Primary Containment Isolation K3.10 Importance 2.9 System/Nuclear Steam Supply Rating Sh Ut-Off 0
The plant is shutdown 0
0 0
RWCU system isolates 0
0 RPV pressure is 700 psig An I&C tech causes drywell pressure transmitter REO4A to fail upscale REO4A has been returned to service and drywell pressure is I.2 psig RWCU pressure is 140 psig Filter bypass valve V-16-83 is OPEN SRO 3.1 Based on the above, the RWCU system SHOULD (1) and the following actions are required, in the stated sequence, to open V-16-1:
(2)
Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on the following:
A.
C.
Explanation:
D. -
AN High pressure isolation setpoint for primary and redundant isolation circuits is 130 psig. It takes two (one-out-of-two twice) high drywell pressure signals to cause an isolation. Therefore:
(1 )
have isolated (2) to approximately 80 psig (1 )
NOT have isolated (2)
RESET pushbutton on 4F (1 )
have isolated (2) pressure isolation keylock in A/B Battery Room, and reduce RWCU pressure to Depress DW ISOLATION RESET pushbutton on 4F, and reduce RWCU pressure Reduce RWCU pressure to approximately 80 psig, and depress DW ISOLATION Depress DW ISOLATION RESET pushbutton on 4F, reset the redundant high approximately 80 psig (1)
NOT have isolated (2)
RESET pushbutton on 4F, and reset the redundant high pressure isolation keylock in Reduce RWCU pressure to approximately 80 psig, depress DW ISOLATION A/B Battery Room
References to be provided during exam:
None Learning Objective 00252 Question Source Bank 1 Modified Bank I I New Question Cognitive Memory or Fundamental Comprehension or Level:
Knowledge Analysis X
X
Knowledge and Ability Reference Information RO 223002 Primary Containment Isolation A4.01 Importance 3.6 System/Nuclear Steam Supply Rating Shut-Off SRO
3.5 Question
Given the following:
~~~
~
Ability to manually operate and/or monitor in the control room:
A plant shutdown is in progress The drywell is being purged with air The Mode Switch is in RUN Valve If power is lost to VMCC 1 B2, which of the following isolation valves will close?
A.
B.
C.
D.
Air Supply to DW (V-28-42, -43) ONLY DW Vent/Purge Valves (V-27-1, -2, -3, -4) ONLY DW Sump Valves (V-22-28, -29) ONLY DW Equipment Drain Valves V-22-1, -2) ONLY Explanation:
ANSWER:
( B REFERENCE(S):
I Loss of power to VMCC 182 will result in deenergizing PAIPP-2, which 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:
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.)
Inst. pwr restoration RAP 10F-4-k I RAP C-4-g, ABN-48 I 3024.,0f References to be None Learning Objective 00394 Question Source Level:
Question Cognitive Bank I Modified Bank 1 1 New
[XI Knowledge Analysis Memory or Fundamental Comprehension or
[XI
Knowledge and Ability Reference Information RO 239002 ReliefBafety Valves K5.02 Importance 3.7 Rating
- u.
n SRO 3.8 (2) 1,375 (1) an MSlV Closure Knowledge of the operational implications of the following concepts as they apply to RELIEFKAFETY VALVES:
REFERENCE(S, Safety function of SRV operation Explanation:
A-B.
UFSAR 5.2.2.4 Safety valves are designed to ensure peak pressure does not exceed 1,375 (1)
(2) 1,250 (1) an MSlV Closure (2) 1,250 (1) a Turbine Trip with ATWS a Turbine Trip with ATWS 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. The ref ore:
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 Obiective 00515,01028 Question Source Question Cognitive Bank I Modified Bank I I New X
Memory or Fundamental I X I Comprehension or Level:
I Knowledge I Analysis
Knowledge and Ability Reference Information RO 259002 Reactor Water Level Control Al.01 Importance 3.8 System Rating I Reactor water level parameters associated with operating the REACTOR WATER LEVEL CONTROL SRO 3.8 SYSTEM controls including:
Question:
Given the following:
A.
B.
C.
D.
140inches 160inches 162 inches 164 inches The plant is at 100% power and stable The feedwater LEVEL TRANSMITTER SELECTOR switch is in AUTO The A white light is LIT The AUTO white light is LIT The B white light is OUT The C amber light is OUT GEMAC A is indicating 165 inches GEMAC B is indicating 162 inches GEMAC C is indicating 164 inches Master FW level controller is in AUTO at 165 inches References to be If GEMAC A fails to 140 inches, what reference level will digital feedwater use to control RPV level?
None Learning Objective Explanation:
10446 I
I RAP J-8-c 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 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.
Question Source Question Cognitive Level:
Bank I Modified Bank I I New X
Memory or Fundamental Comprehension or X
Knowledge Analysis
Question #
I43 Examination Outline Cross-reference
~~
Level I RO I Tier #
I 2 I Group# I 1 Knowledge and Ability Reference Information IRO lSR0 cause-effect relationships between STANDBY GAS TREATMENT SYSTEM and the Importance 2.8 1 Ratina I
I 3.1 261 000 Standby Gas Treatment System Process radiation monitoring system Knowledge of the physical connections and/or I C.
D.
Following:
Question:
Given the following:
References to be Standby Gas has started on a high drywell pressure STANDBY GAS SELECT switch is in the SYS 1 position None 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?
Learning Objective A. I #1 SGTS will remain operating, and #2 SGTS will automatically start 10445 B. I #1 SGTS will shutdown, then SGTS #1 and #2 will re-initiate.
Question Source Bank I Modified Bank I I New X
ANSWER:
I (
REFERENCElS Question Cognitive Level:
Ex p I an ati on :
Memory or Fundamental Comprehension or X
Knowledge Analysis RAP 1OF-1-f I Procedure 330 On an automatic initiation of SGTS, the initiation signals are sealed in.
Because of this, subsequent initiation signals will NOT put the SGTS through a re-initiation sequence. Therefore:
A is incorrect because system 2 fan will secure after the initial initiation 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 D is incorrect, as #1 SGTS will not go through a re-initiation sequence.
.~
Knowledge and Ability Reference Information 261 000 Standby Gas Treatment System A4.03 Importance Rating RO SRO 3.0 3.0 0
0 0
0 A manual start of Standby Gas Treatment System (SGTS) is in progress The STANDBY GAS SELECT switch is in SYS II position All procedure prerequisites have been verified and EF-1-9 is taken to the HAND position NO other actions are taken Ability to manually operate and/or monitor in the control room:
FIVE (5) minutes later, SGTS I orifice valve, V-28-24 will be SGTS II orifice valve, V-28-28 will be (1) and (2)
Fan A.
B-c-
Dm REFERENCE(S Explanation:
(1)
CLOSED (2)
CLOSED (1)
CLOSED (2)
OPEN (1)
OPEN (2)
CLOSED (1)
OPEN (2)
OPEN References to I 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:
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 I None provided during exam:
Learning 1 10445
Question Source Bank 1 Modified Bank 1 I New Question Cognitive Memory or Fundamental I X I Comprehension or X
Level:
I Knowledge I Analysis
Knowledge and Ability Reference Information 262001 A.C. Electrical Distribution K1.01 Importance Rating The plant is at 100% power and steady At time T=O seconds, Annunciator T-3-a, BUS 1 C VOLTS LO is received Bus 1C is reading 3750 volts RO SRO 3.8 4.3 Based upon these conditions, EDG #1 will fast start at time (1) and 41 60V breaker 1 C will trip at time (2)
Knowledge of the physical connections and/or cause-effect relationships between A.C.
ELECTRICAL DISTRIBUTION and the following:
Emergency generators (diesel/jet)
Explanation:
A.
cm D*
I I RAP T-3-a I RAP T-4-a I [ref #3]
For low voltage (<3830 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 1 C will trip. For lo-lo voltage (0 volts per RAP T-4-a), the EDG will fast start after 3 seconds and breaker 1 C will trip. Therefore, since this is a low voltage condition:
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 (1 )
T=O seconds (2)
T=3 seconds (1)
T=3 seconds (2)
T=3 seconds (1 )
T=3 seconds (2)
T=l 0 seconds (1 )
T=l 0 seconds (2)
T=lO seconds References to be None Learning Objective 01086,01087
Question Source Bank I Modified Bank I I New X
Question Cognitive Memory or Fundamental X Comprehension or Level:
Knowledae Analvsis
Knowledge and Ability Reference Information 262001 A.C. Electrical Distribution A201 Importance Rating A plant startup is in progress The main generator has just been synchronized to the grid Reactor power is 25%
Electrical loads have been shifted to the Auxiliary Transformers Breaker 1 A and 1 B control switches are red-flagged Breaker S1 A control switch is green-flagged Breaker S1 B control switch is red-flagged Five (5) minutes later, the Main Turbine trips RO SRO 3.4 3.6 Which of the following describes the plant response, AND what actions are required?
Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A. I Reactor Dower is steadv at 25%. Derform a Dlant shutdown IAW Procedure 203.
Turbine/generator trip B. I Reactor Dower is less than 25%. Derform a $ant shutdown IAW Procedure 203.
C.
D.
Reactor power is steady at 25%, scram the reactor and enterABN-1.
Reactor power is less than 25%, scram the reactor and enter ABN-1.
ANSWER:
I D REFERENCE(S):
Procedure 337 1 ABN-2 Explanation:
A turbine trip under these conditions will result in a loss of 41 60V buses 1A and 1 C, because S1 B 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 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 D is correct References to be None
Level:
I Knowledge L
I Question Cognitive I Memory or Fundamental-1 I Comprehension or I X 1
I Analysis
Question ## I 47 Examination Outline Cross-reference A2.01 Importance Rating Level 1 RO I Tier ##
1 2 I Group# I 1 Knowledge and Ability Reference Information IRO l S R 0 2.6 2.8 262002 Uninterruptable Power Supply (A. C./D. C.)
Under voltage A.
B.
c-Dm Degraded cabling from VMCC 182 to the VACP-1 Auto Transfer Switch has resulted in the following voltages supplied to the switch:
(1)
LIT (2) 7 days (1)
LIT (2) 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> (1)
EXTINGUISHED (2) 7 days (1)
EXTINGUISHED (2) 96 1 0
VMCC 1A2 power supply is 460 VAC 0
VMCC 1 B2 power supply is 250 VAC References to be Based upon the above, the VACP-1 PWR XFER alarm on 9XF will be we can continue operating with this condition for up to shutdown is required.
(1)
, and (2) before a plant None lurs REFERENCE(S Explanation:
I RAP 9XF-3-c Normal power supply to VACP-1 ATS is VMCC 1 B2. 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 182 within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, or the reactor shall be placed in cold shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This is a GL 91-1 1 concern. Therefore:
A is incorrect, as 7 days is longer than 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> B is correct C is incorrect due to alarm not in and longer than 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> D is incorrect due to alarm not in
Question Source Question Cognitive Level:
Bank 1 ModifiedBank I I New X
Memory or Fundamental Comprehension or X
Knowledge Analysis
Knowledge and Ability Reference Information 263000 D.C. Electrical Distribution K4.02 Importance Rating RO SRO 3.1 3.5 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 Knowledge of D.C. ELECTRICAL DISTRIBUTION design feature(@ and/or interlocks which provide for the following:
The RWCU System will...
Breaker interlocks, permissives, bypasses, and cross ties A.
B.
C.
D.
Explanation:
isolate, and RWCU pump A will trip isolate, and RWCU pump B will trip NOT isolate, and RWCU pump A will trip 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:
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 be None Learning Objective 01 127,10445 Question Source Bank I Modified Bank I I New Question Cognitive Memory or Fundamental Comprehension or Level:
Knowledge Analysis X
X
i-Knowledge and Ability Reference Information 263000 D.C. Electrical Distribution A3.01 Importance Rating RO SRO 3.2 3.3 0
0 Line 1 (+) lamp is EXTINGUISHED Line 2 (-) lamp is BRIGHTLY LIT Ability to monitor automatic operations of the D.C.
ELECTRICAL DISTRIBUTION including:
This indicates a ground on C1 Battery Charger will be (2) for these conditions.
(1 )
, and the GROUND DETECTED red light on the Meters, dials, recorders, alarms, and indicating lights A-B-
c*
Dm Explanation:
(1)
Line 1 (+)
(2)
LIT (1)
Line 2 (-)
(2)
LIT (1)
Line 1 (+)
(2)
(1)
Line 2 (-)
(2)
EXT I NG U I S H ED EXTl N G U I S H E D I RAP U-4-f, pg. 2 I
When a battery ground indicating light goes dimmer or completely out, that References to be indicates that lines voltage potential is approaching (dimmer) or is at ground potential (completely out). The other lines indicating light will correspondingly burn brighter, since its overall potential has risen due to the ground on the other line. Normal configuration for the battery charger indicating lights are ON when there is no problem, and go OUT to indicate the problem. Therefore:
A is incorrect, as the ground detected light will NOT be lit B is incorrect, as the wrong line ground is given, and the ground detected light will NOT be lit C is correct D is incorrect, as the wrong line ground is given None
Question Source Bank 1 Modified Bank 1 I New X
Question Cognitive Memory or Fundamental Comprehension or X
10 CFR Part 55 Content: I 55.41 1 (b) (7)
I 55.43 I Level:
Knowledge Analysis
Knowledge and Ability Reference Information 264000 Emergency Generators K3.01 Importance (DieseVJet)
Rating 0
0 0
0 Drywell pressure is 3.5 psig and rising Breaker S1A failed to close when the Main Generator tripped 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 RO SRO 4.2 4.4 If no operator action is taken, which of the following explains the response of the Core Spray system and the EDG?
A.
B.
C.
D.
NZOl A and NZ03A will...
trip due to EDG trip on Hi Temp THEN NZO1 C will automatically start trip due to EDG trip on Hi Temp, AND NZO1 C will NOT automatically start run until diesel failure occurs THEN NZOlC will automatically start run until diesel failure occurs, AND NZO1 C will NOT automatically start References to be provided during exam:
Explanation:
None I
I RAPT-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 1 C will deenergize, and the backup CS main pump (NZO1 C) will automatically start when system 1 pressure drops below 100 psig. NZ03C 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 Learning Objective 00303
Question Source Bank I Modified Bank I I New Question Cognitive Memory or Fundamental I I Comprehension or
[XI
[XI Level:
I Knowledge I Analysis
Knowledge and Ability Reference Information RO 300000 Instrument Air G 2.1.23 Importance 3.9 Rating Question:
Given the following:
SRO 0
The reactor is operating at 100% power 1-1 air compressor is the LEAD compressor 0
1-2 air compressor is the LAG compressor 1-3 air compressor is available A loss of USS 1Al occurs 0
Service Air pressure lowers to 78 psig A.
- 8.
C.
D.
Confirm ONLY 1-2 compressor is running IAW ABN 35, Loss of Instrument Air Confirm 1-2 and 1-3 compressors are running IAW ABN 35, Loss of Instrument Air.
Isolate dryers, pre-filters and post-filters JAW M-3-b, RCVR 2 / INST AIR PRESS LO Verify Service Air Valve, V-6S-2, is isolated IAW M-2-b, SVC AIR DISCH VLV CLOSED ANSWER:
l B REFERENCE(S):
ABN-35 1 M-2-b, M-3-b, M-7-b I [ref #3]
References to be provided during exam:
None
[ref prv #2]
Learning Objective 10453 Question Source Bank I Modified Bank I I New Level:
Knowledge Analysis Question Cognitive Memory or Fundamental Comprehension or
[XI
[XI 55.41 10 CFR Part 55 Con tent :
(b) (1 0) 55.43
Knowledge and Ability Reference Information 300000 Instrument Air K5.01 Importance Rating Based on the above conditions, what action is required?
RO SRO 2.5 A. I Scram the reactor immediatelv IAW ABN-35. Loss of Instrument Air Knowledge of the operational implications of the following concepts as they apply to the Instrument Air:
B. I Press the Remote Start switch for 1-1 air comtxessor IAW alarm rewonse M-5-a Air Compressors
~
C.
D.
~~
~
Scram the reactor after two or more rods move in IAW ABN-35, Loss of Instrument Air Press the Remote Start switch for 1-2 air compressor IAW alarm response M-5-b ANSWER:
I A REFERENCE(S):
ABN-35 I [ref #2]
I [ref #3]
References to be provided None during exam:
[ref prv #2]
Question Source Bank I Modified Bank I [XI I New Question Cognitive Level:
Memory or Fundamental [XI Comprehension or Knowledge Analysis 55.41 (b) (1 0) 10 CFR Part 55 Content:
55.43
~-~~~
Question # I53 0
0 0
0 The TBCCW DISCH PRESS L O alarm actuates.
The TBCCW SURGE TANK LVL HVLO annunciator alarms.
All TBCCW pumps are running.
TBCCW surge tank level is confirmed to be low
~
~
~
~~~
~
~
~
~
What action is required?
Knowledge and Ability Reference Information 400000 Component Cooling Water G 2.4.4 Importance System Rating RO SRO 4.0 I D is incorrect, this action would be for reduced cooling capability.
References to be provided I None I [ref Drv #21 A.
B.
C.
D.
I during exam:
Learning I 10450 Scram the reactor and execute ABN-1, Reactor Scram Commence a normal plant shutdown IAW procedure 203, Plant Shutdown Perform a rapid power reduction IAW procedure 202.1, Power Operations Maximize TBCCW flow IAW procedure 309.1, Turbine Building Closed Cooling Water System ANSWER:
( A REFERENCE(S):
ABN-20 I RAP Q-1 -f I [ref #3]
Question Source Question Cognitive Level:
Bank I Modified Bank I [XI I New Memory or Fundamental [XI Comprehension or Knowledge Analysis 55.41 10 CFR Part 55 Content:
(b) (1 0) 55.43
Knowledge and Ability Reference Information 201 001 Control Rod Drive Hydraulic Al.06 Importance System Rating Given the following:
Reactor Power is 100%
0 Alarm H-8-c, ACCUMULATOR PRESS LO/LEVEL HI, comes in for HCU 38-15 The local test switch is depressed for HCU 38-1 5 and the light remains ON Ability to predict and/or monitor changes in parameters associated with operating the Control Rod Drive Hydraulic System controls including:
Based on the above, the alarm is due to rod scram time will be (1) and (2)
HCU pressureAeveI (1) low pressure (2) slower (1) high water level (2) slower (1 )
low pressure (2) the same (1) high water level (2) the same A.
B.
C.
D.
ANSWER:
I A REFERENCE(S):
I [ref #3]
Explanation:
References to be provided during exam:
If thelight 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.
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.
D is incorrect, it is not due to high level. and scram time will be slower None
[ref prv #2]
Learning 0 bjective 02419,10449
Question Source Bank I Modified Bank I [XI 1 New Level:
Knowledge Analysis 10 CFR Part 55 Content:
Question Cognitive Memory or Fundamental Comprehension or
[XI 55.41 (b) (6) 55.43
Knowledge and Ability Reference Information 202001 Recirculation System A4.01 Importance Rating 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 RO SRO 3.7 What is the NEXT required action?
Ability to manually operate and/or monitor in the control room Recirc pumps A.
B.
C.
D.
Immediately commence a normal plant shutdown Close the discharge valve from its MCC Close the pump suction valve from Panel 3F Close the pump discharge bypass valve from Panel 3F Explanation:
A is incorrect, plant shutdown not required yet.
B is incorrect, not performed until suction valve is closed.
C is the correct answer, shut suction valve is next action IAW ABNQ.
D is incorrect, close suction valve from panel 3F is next action.
References to be provided during exam:
None
[ref prv #2]
Learning Objective 10450 Question Source Question Cognitive Level:
Bank 1 Modified Bank I [XI I New Memory or Fundamental [XI Comprehension or Knowledge Analysis 55.41 10 CFR Part 55 Con tent :
(b) (1 0) 55.43
\\.- -
Knowledge and Ability Reference Information 202002 Recirculation Flow Control K6.01 Importance System Rating RO SRO 2.8 0
Plant is operating at 100% power 0
DCC-X computer is CONTROLLING DCC-Y computer is 00s 0
Power to the DCC-X computer fails Knowledge of the effect that a loss or malfunction of the following will have on the Recirculation Flow Control System:
What is the effect on the Recirculation Flow Control System?
A.C. power A.
B.
C.
D. 1 Control is transferred to the Local Manual Stations Recirc flow lowers to minimum The recirc pump scoop tubes lockup Control is transferred to the Moore Stations ANSWER:
1 C 1
Explanation:
I REFERENCE(S):
1 RAP J-1-c I [ref #2]
1 [ref #3]
I DCC-X power supply is CIP-3, which is 120 Vital AC, powered from Vital MCC 1 B2. DCC-Y power supply is PSP-1, which is 120 Vital AC, powered from Vital MCC 1A2.
A is incorrect, recirc flow remains approximately the same B is incorrect, electrical signal lockup is disabled; air lockup is not in effect.
C is the correct answer, control is transferred to the Moore Stations.
D is incorrect, local manual stations are activated manually.
References to be provided during exam:
None
[ref prv #2]
Learning 0 b jective 00226 Question Source Question Cognitive Level:
Bank I Modified Bank I [XI 1 New Memory or Fundamental [XI Comprehension or Knowledge Analysis
W Knowledge and Ability Reference Information 21 4000 Rod Position Information System K5.01 Importance Rating RO SRO 2.7 Knowledge of the operational implications of the following concepts as they apply to the Rod Position Information System:
Question:
Reed switches Given the following:
Explanation:
Plant is conducting rod swaps at 90% power A control rod is driven from position 48 to position 38 Reactor power lowers as the rod is inserted The Rod Control switch is released as the rod passes position 39 Upon release of the Rod Control switch the rod position display indicates black-black Reactor power remains steady when the Rod Control switch is released 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)
C is the correct answer, if the reed switch is stuck/failed it will not indicate the position.
D is incorrect, the rod would indicate 39.
What has occurred?
References to be provided during exam:
A. I The rod is uncoupled None
[ref prv #2]
B. I The rod is at position 00 Learning Objective C. 1 The reed switch has failed 00726 D. I The rod stuck at position 39 ANSWER:
IC Question Source Question Cognitive Level:
Bank I Modified Bank I 1 New
[XI Memory or Fundamental [XI Comprehension or Knowledge Analysis 55.41 (b) (7) 10 CFR Part 55 Content:
55.43
Question # I58 Examination Outline Cross-reference Level
[ RO I Tier #
12 I Group# 12 Knowledge and Ability Reference Information 21 5001 I Traversing In-Core Probe I K4.01 I Importance RO SRO 3.4 Knowledge of Traversing In-Core Probe design feature(s) and or interlock(s) which provide for the followina:
Question:
I Rating Primary Containment Isolation Given the following:
While an operator is inserting a TIP into the core, a containment isolation signal is received.
A.
B.
C.
D.
The TIP purge valve (1) and the TIP (2)
(1) remains open (2)
(1) shuts (2)
(1) remains open (2)
(1) shuts (2) drive automatically shifts to reverse, withdraws the detector to the in-shield position and the ball valve closes.
drive automatically shifts to reverse, withdraws the detector to the in-shield oosition and the ball valve closes.
shear valve fires to cut the detector cable and seal the guide tube.
shear valve fires to cut the detector cable and seal the guide tube.
Procedure 405.2, 31 2.9 REFERENCE(S):
[ref #3]
[ref #21 Explanation:
References to be provided during exam:
None
[ref prv #2]
B is the correct answer, IAW 405.2.
C is incorrect, the purge valve will shut and the shear valve is not used unless the cable cannot be retracted.
D is incorrect, the shear valve is not used unless the cable cannot be retracted..
Learning 0 b jective 10444 Question Source Question Cognitive Level:
Bank I [XI I Modified Bank I I New Memory or Fundamental [XI Comprehension or Knowledge Analysis 55.41 10 CFR Part 55 Content:
(b) (7) 55.43
Knowledge and Ability Reference Information 21 9000 Torus/Suppression Pool Cooling K2.02 Importance Mode Rating 0
Containment Spray pump 51 C and ESW pump 52C are in the Torus Cooling Mode T-2-e, MN BRKR 1D 86 LKOUTTRIP, is received RO SRO 3.1 Containment Spray/ESW pumps...
A.
B.
C.
D.
51 C and 52C remain operating. 51 A and 52A will be available as backups 51 C and 52C remain operating. 51 D and 52D will be available as backups 51 C and 52C trip. 51A and 52A will be available as backups 51 C and 52C trip. 51 D and 52D will be available as backups REFERENCEE):
wovided None Explanation:
[ref prv #2]
References to br Learning 0 bjective 1 Proc. 341, Att. 6 I [ ref #2]
I [ref #3]
51/52 A and B are powered from bus 1 C, 51/52 C and D are powered from bus 1 D. [unlike Core Spray power supplies]
A is incorrect, 51 C 52C will trip.
B is incorrect, 51 C 52C will trip and 51 D 52D will have no power.
C is the correct answer.
10444 Question Source Bank I Modified Bank 1 1 New Question Cognitive Memory or Fundamental [XI Comprehension or Level:
Knowledge Analysis
[XI 55.41 10 CFR Part 55 Content:
(b) (7) 55.43
223001 1 Primary Containment System and I Auxiliakies 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 sonsequences of those abnormal conditions or Dperations.
Question:
A2.10 Importance Rating 3.6 3.8 High drywell temperature A-B-
c=
D.
Given the following:
(1) 150deg. F (2)
(1) 281 deg. F (2)
(1) 150deg. F (2)
(1) 281 deg. F (2)
Emergency Depressurization Enter Primary Containment Control ONLY Enter Primary Containment Control, AND scram the reactor IAW ABN-1 Enter Primary Containment Control, AND commence a plant shutdown IAW 203.1 Enter Primary Containment Control, RPV Control - No ATWS, AND perform an D
The plant is operating at 100% power The supply breaker for MCC 1 A23 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 The DW TEMP HI alarm, C-8-h is alarming and will NOT clear The STA has confirmed the alarm is valid References to be None Explanation:
Learn i n g 0 bject ive 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 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 03000,03002
v Question Source Bank I Modified Bank 1 1 New X
Question Cognitive Memory or Fundamental Comprehension or X
Level:
Knowledae Analvsis
Question # I61 Examination Outline Cross-reference Level I RO I Tier #
I 2 I Group# 12 Knowledge and Ability Reference Information 233000 Fuel Pool Cooling/Cleanup A3.02 Importance Rating RO SRO 2.6 Ability to monitor automatic operations of the Fuel Pool Cooling/Cleanup including:
Question:
Given the following:
Pump trip(s)
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 A.
B.
C.
D.
The fuel pool makeup valve opens The fuel pool pump trips on low flow The fuel pool pump trips on low surge tank level The low surge tank level pump trip is bypassed REFERENCE(S):
G-7-a, Procedure 31 1
[ref #3]
[ref Explanation:
References to be provided during exam:
None
[ref prv #2]
Learning Objective 08570, 10441 Question Source Question Cognitive Level:
Bank I Modified Bank I [XI I New Memory or Fundamental [XI Comprehension or Knowledge An a I y s i s 55.41 10 CFR Part 55 Content:
(b) (7) 55.43
I--
Knowledge and Ability Reference Information 245000 Main Turbine Generator and K3.08 Importance Auxiliary systems Rating RO SRO 3.7 3.8 0
The plant is operating at 100% power 0
A leak develops in the vacuum sensing bellows for B main condenser 0
On control room panel 5F/6F, the indicated vacuum for B condenser goes from 28.7 to 12 in. Hg Knowledge of the effect that a loss or malfunction of the Main Turbine Generator and Auxiliary systems will have on the following:
Reactorrrurbine pressure control system Explanation:
A.
B.
C.
D.
i.e., the bellows for A condenser feeds the bellows for B condenser, which feeds the bellows for C. Any ONE of these bellows reaching the setpoint of 22 will cause VT-1 to actuate, causing a main turbine trip and a reactor scram on low vacuum. Any ONE bellows reaching the setpoint of 1 0 will cause VT-2 to actuate, tripping the bypass valves closed. Therefore; A is incorrect, turbine will trip.
B is incorrect, turbine will trip, C is incorrect, the bypass will still open greater than 10 in. Hg.
The turbine will NOT trip, the turbine bypass valves will NOT open The turbine will NOT trip, the turbine bypass valves will open The turbine will trip, the turbine bypass valves will NOT open The turbine will trip, the turbine bypass valves will open D is correct,.
Referencestobe provided I None I [ref Drv #21 ANSWER:
I D REFERENCES):
I I
during exam:
Learning I 10444.01723 RAP Q-2-c 1 [ref #2]
I [ref #3]
Question Source Question Cognitive Level:
Bank I Modified Bank I [XI I New Memory or Fundamental [XI Comprehension or Knowledge Analysis 55.41 10 CFR Part 55 Content:
(b) (7) 55.43
Knowledge and Ability Reference Information 256000 Reactor Condensate system G 2.1.28 Importance Rating 0
0 0
0 0
0 SJAEs are in service Reactor startup is in progress All 8 IRMs are in Range 8 RPV pressure is 150 psig and rising slowly A Condensate pump is in service Main Turbine heatup is in progress RO SRO 3.2 Which of the following would be the consequence if the hotwell level spill and makeup valves failed closed?
A.
B.
C.
D.
Reactor feedwater inlet temperature would rise.
The running CRD pump would trip on low suction pressure.
The A Condensate pump temperatures would rise.
Main Turbine exhaust hood temperatures would rise.
REFERENCE(S):
Explanation:
References to be provided during exam:
I FSAR.
I [ref #21 I [ref #31 None
[ref prv #2]
During the stated conditions, there would be no condensate flow to the RPV (all injection is from CRD). The spill valves provide minimum flow for the condensate pumps, so a loss of the spill and makeup capability will result in the A condensate pump operating at dead-headed conditions. Therefore:
A is incorrect, as the spill/makeup lines do not provide input to fw heaters.
B is incorrect, as the water quality line to the CRD pumps is upstream of the spiWmakeup valves, so it is still providing preferred suction to CRD.
C is the correct answer, provides for condensate pump min flow D is incorrect, does not provide exhaust hood spray function.
Learning 0 b jective 10435
Question Source Level:
Question Cognitive Bank I ModifiedBank I I New
[XI Knowledge Analysis Memory or Fundamental Comprehension or
[XI 55.41 10 CFR Part 55 Content:
(b) (4) 55.43
Knowledge and Ability Reference Information 256000 I Reactor Condensate system I G 2.1.28 I Importance Question # I63 Examination Outline Cross-reference Level I RO I Tier #
12 I Group# 12 RO SRO 3.2 Learning 0 b jective I
I I Ratina I
I 10435 Knowledge of the purpose and function of major system components and controls Question:
Given the following:
0 SJAEs are in service Reactor startup is in progress All 8 IRMs are in Range 8 RPV pressure is 150 psig and rising slowly A Condensate pump is in service Main Turbine heatup is in progress Which of the following would be the consequence if the hotwell level spill and makeup valves failed closed?
A. I Reactor feedwater inlet temDerature would rise.
B. I The runnina CRD DumD would triD on low suction Dressure.
C. I The A Condensate DumD temDeratures would rise.
D. I Main Turbine exhaust hood temperatures would rise.
ANSWER:
IC -
I REFERENCE(S):
I BR 2003, sheet 1 I During the stated conditions, there would be no condensate flow to the RPV Explanation:
(all injection is from CRD). The spill valves provide minimum flow for the condensate pumps, so a loss of the spill and makeup capability will result in the A condensate pump operating at dead-headed conditions. Therefore:
A is incorrect, as the spilVmakeup lines do not provide input to fw heaters.
B is incorrect, as the water quality line to the CRD pumps is upstream of the spill/makeup valves, so it is still providing preferred suction to CRD.
C is the correct answer, provides for condensate pump min flow D is incorrect, does not provide exhaust hood spray function.
References to be provided I None I [ref prv #21
Knowledge and Ability Reference Information 259001 Reactor Feedwater System K1.08 Importance Ratina RO SRO 3.6
~~. Knowledge of the physical connections and/or I
ANSWER:
1B REFERENCE(S):
1 Reactor water level control system cause-effect relationships between Reactor Feedwater System and the Procedure 31 7 I [ref #21 I [ref #3]
Question:
Given the following conditions:
Explanation:
0 0
0 0
0 Plant is operating at 65% power Master feedwater controller in "AUTO", setpoint is 163.5 in. TAF Feedpump 1 A is running with its flow controller in "AUTO" Feedpump 1 B is running with its flow controller in "MAN" The flows in the operating feed strings are equal A is incorrect, the B MFRV does not move.
B is the correct answer, the setpoint is lowered and the B MFRV does not move.
C is incorrect, the setpoint is lowered.
D is incorrect, the setpoint is lowered.
With the Master feedwater controller selected to the "S" display, the adjustment knob is rotated in the COUNTER-CLOCKWISE direction.
References to be provided None during exam:
What will occur?
[ref prv #2]
A. I Reactor level setDoint is lowered. the A and B MFRVs will close Learning Objective B. I Reactor level setDoint is lowered, ONLY the A MFRV will close 10447 C. I Reactor level setDoint is raised. the A and B MFRVs will oDen Question Source Level:
Question Cognitive Bank I [XI I Modified Bank I 1 New Knowledge Memory or Fundamental Comprehension or
[XI An a I ys i s 55.41 10 CFR Part 55 Con tent:
(b) (7) 55.43
Knowledge and Ability Reference Information
( R O 272000 Radiation Monitoring System Al.01 I Importance 13.2 I
Ability to predict and/or monitor changes in parameters associated with operating the RAD I AT1 ON MON IT0 R I NG SYSTEM controls SRO
3.2 including
Question:
I Ratina I
I Lights, alarms, and indications associated with normal operations 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 1 100 mr/hr at 101 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Off-gas bypass valve V-7-31 will...
Knowledge and Ability Reference Information RO 2.1 Conduct of operations 2.1.2 importance 3.0 Rating Given the following:
0 0
Since leaving shift, the RO has performed license duties as follows:
0 9/4/2004; 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0
10/1/2004; 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Which of the following is correct?
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 SRO 4.0 A 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
Knowledge and Ability Reference Information 2.1 Conduct of operations 2.1.33 Importance Rating
~
~~~~
~
~~~
The plant is operating at 100% power with the following integrator readings:
0400 I
385941 I
728949 Time DWEDT Integrator DW Sump Integrator 0000 384789 728445 12/6/04 0000 391 493 731 499 0400 392603 732651 u
ANSWER:
REFERENCEM A.
B.
C.
D I T.S. 3.3.D.3 I
I Place the reactor in the shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Place the reactor is the cold shutdown condition within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Reduce the leak rate below the allowable limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in the cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Identify the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in the cold shutdown condition within the followina 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Explanation:
Learning Objective References to I 10451 DWEDT leakage (identified) is 4.8 gpm on 12/5 and 4.625 gpm on 12/6.
DW Sump leakage (unidentified) is 2.1 gpm on 12/5 and 4.8 on 12/6.
Theref ore:
A is incorrect because this would be the action taken for loss of unidentified leak rate determination B is incorrect because this is the action to take if there are no T.S. LCO for the condition (LCO 3.0.A)
C is incorrect, as this is the action for greater than 5 gpm UlLR D is correct I TS 3.3 Question Source Level:
Question Cognitive Bank I Modified Bank I I New X
Memory or Fundamental Comprehension or X
Knowledge Analysis
Knowledge and Ability Reference Information 2.1 Conduct of operations 2.1.23 Importance Ratina Ability to perform specific system and integrated plant procedures during different mode of plant operation.
I Steam tables Given the following:
0 The plant is shutdown 0
Shutdown Cooling loops A and B are in service 0
At 9:30 AM, all RBCCW is lost, reactor pressure is 41 psig 0
At 9:50 AM, reactor pressure is 70 psig Based upon the above, the heatup rate is approximately...
I [ref #3]
A. I 28 dea. F Der hour References to Lz B. I 35 dea. F Der hour Steam tables C. I 84 dea. F Der hour Learning Objective D. 1 105 dea. F 00026,00042 Explanation:
Question Source Question Cognitive Level:
er hour Bank I Modified Bank I I New X
Memory or Fundamental Comprehension or X
Knowledge Analysis psia.)
'c-Knowledge and Ability Reference Information RO 2.2 Equipment control 2.2.1 Importance 3.7 Rating SRO 3.6 A.
B.
C.
D.
Explanation:
When SRM 24 = 440 cps When SRM 21 = 600 cps The reactor is not critical after reaching the +I % dk sequence step in the ECP.
The reactor is not critical after the first four control rod groups have been withdrawn.
position 06 and 24 B is incorrect, as greater than 3 but less than 4 doublings only requires 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 provided during exam:
None Learning Objective 10447
1 Question Source Bank I Modified Bank I I New X
Question Cognitive Memory or Fundamental Comprehension or X
10 CFR Part 55 Content: I 55.41 I (b) (1)
I 55.43 I Level:
Knowledge Analysis
Knowledge and Ability Reference Information RO 2.2 Equipment Control 2.2.13 Importance 3.6 Rating A. 1 Sub Clearance SRO 3.8 B. I Clearance ExceDtion ANSWER:
I D REFERENCE(S;\\:
C. 1 TemDorarv Clearance OP-MA-109-101 Explanation:
A is incorrect, plausible but not for this situation B is incorrect, plausible but not for this situation C is incorrect, plausible but not for this situation D is correct, Clearance Suspension covers this situation References to be None Learning Objective C&T lesson plan - obj. #36 Question Source Question Cognitive Level:
Bank I Modified Bank 1 1 New X
Memory or Fundamental X Comprehension or Knowledge Analysis
Knowledge and Ability Reference Information 2.2 Equipment Control 2.2.2 Importance Rating 0
0 The plant is at 60% power and stable The B Recirc loop is idle, all other recirc loops are operating in AUTO All prerequisites have been met to start the B Recirc pump The B MG Set Drive Motor breaker is shut The B MG Set scoop tube is at 100%
The WARM LIGHT for the B Recirc MG Set has just illuminated RO SRO 4.0 3.5 When the B Recirc Pump STRT/NORM pushbutton is depressed...
B.
- c.
D.
A. I the field breaker will close immediatelv. and the SCOOD tube will remain at 100%.
~~~~~~~~
the field breaker will close immediately, and the scoop tube will start running back.
the scoop tube will start running back, and the field breaker will close when the scoop tube passes through the 60% to 50% range.
the scoop tube will start running back, and the field breaker will close when the scoop tube passes through the 40% to 30% range.
Explanation:
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 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 Learn i ng 0 biective 10447 Question Source Question Cognitive Bank 1 Modified Bank I I New X
Memory or Fundamental I X I Comprehension or Level:
I Knowledge I Analysis
+-
Knowledge and Ability Reference Information RO 2.3 Radiation Control 2.3.1 0 Importance 2.9 Rating SRO 3.3 exposure..
Question:
Given the following:
A.
B.
C.
D.
0 You are assigned work in a radiation area You exposure limit is 100 mrem The dose rate in the work area is 30 mr/hr 0
Your assignment will take 90 minutes to complete.
Monitor the dose rate on your ESRD, continue to work Warn other workers, exit the area, notify Rad Pro Wait for your exposure limit to be reached, then exit the area Complete the work assignment, exit the area, notify Rad Pro 10 minutes after entering the work are, your ESRD begins to chirp/beep.
References to be What action is required?
None Learning Obiective NGET Study Guide, pg. 109 REFERENCE(S):
1 A is incorrect, must leave the area Rad Worker training lesson plan, obj. 25, 31 Explanation: I C is is correct, incorrect, must leave the area due to unexpected rad levels Question Source Question Cognitive Bank I Modified Bank 1 1 New X
Memory or Fundamental I X I Comprehension or Level:
I Knowledge 1 Analysis
Knowledge and Ability Reference Information 2.3 Radiation Control 2.3.4 Importance Rating Given the following:
A plant transient has occurred Radiation levels in the Reactor Building have forced an evacuation of the Reactor Building The reactor did NOT scram due to an electrical ATWS All attempts to insert control rods from the Control Room have been unsuccessful It is decided the Scram Air Header must be vented in order to insert control rods B.
C.
D.
What is the MAXIMUM emergency exposure limit allowed under these conditions?
5,000 mrem TEDE 10,000 mrem TEDE 25.000 mrem TEDE A. I 2,000 mrem TEDE Learning 0 bject ive Rad Worker training lesson plan, obj. 17 Explanation:
Question Source 1 Bank I I RP-AA-203 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 (1 0,000 mrem). Therefore:
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 populations I Modified Bank 1 1 New lx I
I None Question Cognitive Level:
I I
I I
Memory or Fundamental X Comprehension or Knowledge Analysis
Knowledge and Ability Reference Information G 2.4.6 Importance Rating 0
A LOCA is in progress 0
Drywell pressure is 50 psig and rising slowly 0
Containment Spray pumps are NOT available 0
Drywell H2/02 monitors have been placed in service and are warming up 0
Torus level is 160 inches and rising slowly 0
The containment is being vented from the Torus through the hardened vent IAW S.P.-35 RO SRO 3.1 Ten minutes later, the following conditions exist:
A.
B.
C.
Dm 0
0 0
Torus level is 180 inches and rising slowly Drywell pressure is 48 psig and rising slowly Drywell H2/02 monitors read 1.7%
(1)
(2)
(1)
(2)
(1)
(2)
(1)
(2)
Shift containment venting to S.P.-33 Vented atmosphere must be processed through SGTS before being released to the environment Shift containment venting to S.P.-33 Hardened vent must be available to purge the containment Shift containment venting to S.P.-32 Vented atmosphere must be processed through SGTS before being released to the environment Shift containment venting to S.P.-32 Hardened vent must be available to purge the containment (1)
(2)
What action must be taken?
What is the basis for this?
Explanation:
As long as containment level is below 348 inches, venting via the Torus is directed to scrub particulates prior to release. The preferred vent path is via the hardened vent, as this path will not cause vent duct failure. However, if hydrogen goes above 1.5%, the hardened vent path must be abandoned, because this vent path goes through the nitrogen purge lineup, which must be available to use as a purge medium to rid the containment of hydrogen and/or oxygen. Therefore:
A is incorrect, because water level is below 348 inches, so venting will be via S.P.-32 and the hardened vent must be available for purging
L-References to be provided None during exam:
[ref prv #2]
Learning Objective c
09546 Question Source Question Cognitive Level:
Bank I Modified Bank I 1 New X
Memory or Fundamental Comprehension or X
Know ledge Analysis 55.41 10 CFR Part 55 Content :
(b) (IO) 55.43
Knowledge and Ability Reference Information 2.4 Emergency Procedures / Plan 2.4.31 Importance Rating Given the following:
RO SRO 3.3 3.4 A small LOCA is in progress Containment Spray System 1 is in the Drywell Spray mode Containment Spray Pump 51 A 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 ANSWER:
[ A REFERENCE(S):
What action occurs as a result of this alarm?
RAP 6-2-a A. 1 Torus Sprav Valve V-21-18 automaticallv closes.
Explanation:
B. I Containment SDrav PumD 51 A automaticallv trios.
A is correct 6 is incorrect, as 51 A only trips on overload or low DW press (.6 psig)
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)
C. 1 Containment Sorav Pump 51A must be manuallv trimed.
References to be None Learning Objective 10444 Question Source Question Cognitive Level:
Bank I Modified Bank 1 I New X
Memory or Fundamental Comprehension or X
Knowledge Analysis
Knowledge and Ability Reference Information RO 295003 Partial or Complete Loss of AC AA2.04 Importance power Rating Question:
SRO 3.7 Given the following:
Ability to determine and interpret the following as they apply to Partial or Complete Loss of AC power 0
0 The reactor is at 100% power Main breaker 1 A trips as a result of a 1 A bus fault.
System One minute after the trip of Bus 1 A, what USSs will be energized and what action is required?
-x
~~
C.
D.
Question #
1 SO2 Perform a rapid power reduction IAW 202.1, Power Operation.
Take manual control of feedwater and restore RPV level IAW ABN-17, Feedwater System Abnormal Condition.
Examination Outline Cross-reference I swsl
[ref #2]
J-1 -f, H-7-e, ABN-17 REFERENCE(S):
I Rating Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument
[ref #3]
interpretation Question:
The plant is operating at 90% power with the following conditions:
References to be provided during exam:
e e
Power ascension using recirculation flow is in progress.
Feedwater pumps A, B and C are in service None
[ref prv #2]
One minute later Feedwater Pump C trips and the following alarms are received:
Learning Objective e
FEED PUMP TRIP C, (J-1-f) a FEED PUMP OL C, (J-2-f) 10450 Which one of the following actions is required?
Question Source I Bank A. I Manuallv scram the reactor IAW ABN-1. Reactor Scram.
I Modified Bank I
I New I rxi B. I Restart the C Feedwater DumD IAW J-1-f. Feed Pumr, TriD.
Question Cognitive Level: Memory or Fundamental
[XI Comprehension or Knowledge Analysis 10 CFR Part 55 Content:
I 55.41 I 55.43 I (b) (5)
Knowledge and Ability Reference Information 295006 I SCRAM I AA2.03 I Importance RO SRO
4.2 Question
Ability to determine and/or interpret the following as they apply to SCRAM:
Given the following:
0 Plant at 100% power 0
0 If left UNCORRECTED, how will the plant respond and what actions are required?
Digital Feed Level Transmitter Selection on 4F is in AUTO A leak develops in the variable leg for the A level input to Digital Feed I Rating Reactor water level A.
B.
c r\\
Level will lower leading to a scram. Execute ABN-1, Reactor Scram Level will rise leading to a turbine trip. Execute ABN-10, Turbine Trip and ABN-1, Reactor Scram Level Transmitter Selection will automatically swap to the B level input. Adjust the level setpoint IAW procedure 31 7 Feedwater System Level Transmitter Selection will substitute 160 in. for input to Digital Feed. Monitor level Explanation:
ANSWER:
I B REFERENCE(S):
For variable leg leak actual 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 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.
D is incorrect, digital feed will not see this as an error.
H-6-f, ABN-10 References to be provided during exam:
None Question Source Bank I Modified Bank I [XI I New Question Cognitive Level: Memory or Fundamental I [XI I Comprehension or I Knowledge
.. I Analysis 10 CFR Part 55 Content:
I 55.41 1 55.43 I (b) (5)
Question #
I SO4 I
Knowledge and Ability Reference Information 29501 9 Partial or Complete Loss of G 2.1.31 Importance Instrument Air Rating RO SRO
3.9 Question
Given the following conditions:
References to be provided during exam:
0 0
0 0
0 Plant is operating at 100% power Instrument air header pressure drops to 0 psig MSlVs closed on low air pressure The reactor scrammed and all rods are fully inserted RPV pressure is 1055 psig and rising slowly None Based on the above conditions, which of the following alternate pressure control actions can be performed from the Control Room?
Learning Objective A. I Direct the use of IC Vent Valves IAW SP-15.
00666 B. I Direct the use of IC Makeup valves IAW SP-11.
Question Source Question Cognitive Level:
C. I Direct the use of RWCU in the Recirculation Mode IAW SP-13.
Bank I Modified Bank I [XI I New Memory or Fundamental I Comprehension or
[Xl D. I Direct the use of RWCU in the Letdown Mode IAW SP-14.
ANSWER:
IB I Knowledge REFERENCEE):
I Analysis 1
I I ABN-35 I RPV Control EOP On a total loss of instrument air, IC vent valves fail closed, RWCU flow 10 CFR Part 55 Content:
I 55.41 I Explanation:
55.43 I (b) (5) control, pressure control and letdown control valves all fail closed.
Therefore:
A is incorrect, as the vent valves cannot be opened B is the correct answer, as accumulators are provided to allow these valves to be opened and makeup established to the ICs.
C is incorrect, as the flow control and pressure control valves cannot be opened.
D is incorrect, as the flow control, pressure control, and letdown control
Question #
I SO5 References to be provided during exam:
I Rating Ability to evaluate plant performance and make operational judgments based on operating characteristics/reactor behavior/instrument interpretation.
Conduct of Operations Question:
Given the following:
None
[ref prv #2]
Reactor is shutdown following 100 days of full power operation Shutdown cooling is in service with all 3 loops Each SDC loop is operating at 2,550 gpm The vessel head has NOT been removed All 5 reactor recirc pumps are secured B recirc loop suction and discharge valves are open All other recirc loops are in the idle configuration RPV level is 162 in. TAF and steady If a Shutdown Cooling pump trips and cannot be restarted, which of the following will occur and what actions are required to mitigate it?
A. I Thermal stratification will occur. Direct raising RPV level to 200 inches.
B. I Thermal stratification will occur. Direct shutting of the B recirc loop discharge valve.
C. I Short-cvclinn will occur. Direct raising RPV level to 200 inches.
D. I Short-cycling will occur. Direct shutting of the B recirc loop discharge valve.
ANSWER:
] A REFERENCE@):
Procedure 305 Whenever SDC is in service with no recirc pumps operating, at least 1 recirc loop 2000-0Ps-3024.27 Explanation:
suction and discharge valves (other than E loop) must be-open for communication between the annulus and shroud, and the E recirc loop suction and discharge valves must be shut (because SDC taps off the E recirc loop.) Because of this requirement, short-cycling through the open loop will be occurring, but it cannot be mitigated. In order to prevent thermal stratification, SDC system flow must be above 7,500 gpm with level between 160 and 165 in. TAF. Since the loss of one SDC pump will result in SDC system flow of 5,100 gpm, RPV level must be raised above 185 in. TAF to promote natural circulation. Therefore:
A is correct B is incorrect, as all 5 loops cannot be idled C is incorrect, as short-cycling is already occurring and is not a result of the SDC pump trip D is incorrect, as short-cycling is already occurring and is not a result of the SDC pump trip, and idling the 5h recirc loop is not allowed
'L' Learning Objective 10450 Question Source Bank I Modified Bank I I New Question Cognitive Level:
Memory or Fundamental I [XI I Comprehension or
[XI
Knowledge and Ability Reference Information 295024 High Drywell Pressure G 2.4.50 Importance Rating RO SRO 3.3 T = 0 minutes; A.
B.
C.
D.
Drywell pressure rises to 3.7 psig Drywell temperature is 140 deg. F Start NZOI A & NZ03A IAW SP-1, Primary Containment initiations and isolations Start NZOI D & NZ03D IAW SP-1, Primary Containment initiations and isolations Secure EDG #1 & #2 locally IAW procedure 341, Emergency Diesel Generators Maximize Drywell Cooling IAW Primary Containment Control T = 1 minute; ANSWER:
I A REFERENCE(S):
Core Spray Main pump B (NZOI B) & Core Spray Booster pump B (NZ03B) are the ONLY Core Spray pumps running All other systems responded as designed RAP B-I -e, I SP-1 I [ref #3]
Which of the following actions is required based on the above conditions?
References to be provided None during exam:
[ref prv #2]
I manually started Learning 0 b jective I B is incorrect, SP-1 directs one main and one booster in each system. 1 D/3D are Explanation: the same system as 1 B/3B.
10450 Question Source Bank I Modified Bank I
I New Question Cognitive Level:
Memory or Fundamental
[XI Comprehension or Knowledge Analysis
[XI 10 CFR Part 55 Content:
I 55.41 I 55.43 I (b) (5)
Knowledge and Ability Reference Information 295025 High Reactor Pressure G 2.1.28 Importance Rating A plant transient resulted in the following:
RO SRO 3.3 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.
IC "B" steam line D/P reaching 300% for 35 seconds.
A.
B.
C.
D.
Based on the above conditions, how will the plant respond?
IC "A1 isolates ONLY. Enter RPV Control - No ATWS.
IC "B" isolates ONLY. Enter Primary Containment Control.
IC " A I initiates and IC "B" isolates. Enter RPV Control - No ATWS.
IC "B" initiates and IC "A" isolates. Enter Primary Containment Control.
ANSWER:
condensate flow.
A is incorrect. B IC isolates Explanation:
RAP C-3-b I [ref #2]
I [ref #3]
References to be provided during exam:
None
[ref prv #2]
Learning Objective 02030 Question Source Question Cognitive Level:
Bank I [XI I Modified Bank I
I New Knowledge Analysis Memory or Fundamental Comprehension or
[XI 10 CFR Part 55 Content:
I 55.41 I 55.43 I (b) (5)
Knowledge and Ability Reference Information 295026 Suppression Pool High Water EA2.01 Importance Temperature Rating RO SRO 4.2 0
0 0
0 RPV water level is 75 in. TAF Drywell pressure is 1.2 psig Torus temperature is 97 deg. F ALL automatic actuations and initiations have occurred Ability to determine and interpret the following as they apply to Suppression Pool High Water Temperature Based on the above conditions, which one of the following actions satisfies ALL the requirements of 2000-EMG-3200.02, Primary Containment Control?
Suppression Pool cooling A.
B.
C.
D.
pumps on the Torus at one time B is incorrect, drywell spray not required.
Explanation:
for ONE containment spray system in the Torus Cooling mode for ONE containment spray system in the Drywell Spray mode for BOTH containment spray systems in the Torus Cooling mode for BOTH containment spray systems in the Drywell Spray mode ANSWER:
I A REFERENCE(S):
I [ref #3]
References to be provided None during exam:
[ref prv #2]
Learning Objective 00446 Question Source I Bank I Modified Bank I
I New I [XI 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 29501 5 Incomplete Scram G 2.4.6 Importance Rating strategies Question:
RO SRO 3.1 4.0 Given the following:
A.
B.
C.
D.
The plant scrammed from 100% power 12 rods remain at notch position 48 All APRMs are downscale IRMs indicate 50% of range 6 Torus Temperature is 82 degrees and steady MSlVs are closed Reactor Pressure is being maintained between 850 & 1000 psig using Isolation Condensers Reactor water level is being maintained between 138 & 175 in. TAF using Feed &
Condensate Terminate and prevent all injection except boron and CRD until reactor power drops below 2%.
Execute Support Procedure 16, then re-open the MSlVs to establish the main condenser as a heat sink.
Terminate and prevent all injection except boron and CRD until RPV water level drops below 30 in. TAF.
Inject liquid poison.
During the next 3 minutes reactor power rises to 6%.
ANSWER:
I C REFERENCE(S):
What is the required action?
EMG-3200.01 B I [ref #2]
I [ref #3]
given to wait for any required MSlV low level isolation bypasses, then terminate and prevent injection, lower level below 30 inches. This direction is independent of any resultant power level drops. Once actions are taken to lower level in this situation, injection is not allowed until level is below 30 inches. Further guidance is given for IeveVpower situations where power is above 2%, heat is being added to the torus through a DW leak or open EMRVs, and level is above TAF. In that situation, level will be lowered below 30 inches, then continue lowering level until power is below 2%, or level reaches TAF, or the heat addition to the torus stops. This is NOT the situation given in this question. Therefore:
A is incorrect, but would be appropriate for IeveVpower issues B is incorrect, but would be appropriate for IeveVpower issues (contained as Explanation:
-v-Learning Objective a conditional statement in the Pressure Control leg)
C is the correct answer.
10450 I D is incorrect because the BllT is not being approached I [ref prv #2]
References to be provided I EOPs w/o entry conditions Question Source Bank I Modified Bank I [XI 1 New Question Cognitive Level: Memory or Fundamental I Comprehension or
[XI I Knowledge I Analysis 10 CFR Part 55 Content:
I 55.41 I 55.43 I (b) (5)
Knowledge and Ability Reference Information 21 5004 Source Range Monitor A2.02 I Importance I
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 mitigate the consequences of those abnormal oDerations:
RO SRO 3.7 I Rating SRM inop condition A.
B' D.
Question:
Given the following conditions:
CAN continue without further action(s); the SRM Rod Block is bypassed at IRM Range 3, IAW H-7-a, ROD BLOCK CANNOT continue without further action@); the SRM Rod Block will NOT clear until IRM Range 8, IAW H-7-a, ROD BLOCK CAN continue without further action@); only 2 SRMs are required to be operable for Startup, IAW Att. 201 -2, Pre-Critical Checkoff CANNOT continue without further action(s); plant procedures will NOT allow a Startup with only 2 operable SRMs, IAW Att. 201 -2, Pre-Critical Checkoff Rx mode switch in "Startup" SRM21 bypassed 0
SRM 22 mode switch is placed in PERIOD All IRMs in range 4 ANSWER:
( B REFERENCE(S):
201, H-7-a I [ref #2]
I [ref #3]
Explanation:
Placing SRM mode switch in PERIOD causes an INOP Rod Block.
A is incorrect, Rod Block will not clear until IRM Range 8 B is the correct answer, Startup cannot continue.
C is incorrect. only 2 SRMs are required to be operable for Startup, IAW Att. 201 -2, Pre-Critical Checkoff, but Rod Block will not clear until IRM Range 8 or switch to OPERATE, rods could not be moved to continue with startup D is incorrect, plant procedures WILL allow a Startup with only 2 operable SRMs.
References to be provided during exam:
None
[ref prv #2]
Learning Objective 03002 Question Source Question Cognitive Level:
Bank I Modified Bank I [XI I New Memory or Fundamental I Comprehension or
[XI I Knowledge I Analysis 10 CFR Part 55 Content:
I 55.41 I 55.43 I (b) (5)
I Knowledge and Ability Reference Information 295032 High Secondary Containment EA2.01 Importance RO Temperatures Rating SRO 3.8 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:
Ability to determine and/or interpret the following as they apply to High Secondary Containment Temperatures 0
0 51 RWCU PMP RM (WEST) indicates 225 deg. F 75 DEMIN VAULT indicates 220 deg. F 75 PRECOAT TANK indicates 230 deg. F 95 IS0 COND (NORTH) indicates 200 deg. F Area temperature Which of the following actions is required based on the above conditions?
--e-Knowledge and Ability Reference Information 295036 Secondary Containment High G 2.4.6 Importance SumpNVater Level Rating RO SRO 4.0 strategies Question:
A.
B.
C.
~
Given the following:
Core Spray system 1 pumps NOT available, enter Primary Containment Control Core Spray system 2 pumps NOT available, enter Secondary Containment Control Containment Spray system 1 pumps NOT available, enter Primary Containment Control Containment Spray system 2 pumps NOT available, enter Secondary Containment Plant is at 100% power The Torus develops a leak Torus water level is 146 in.
Rx Bldg SW Corner Room water level is 24 in. and rising Rx Bldg NW Corner Room water level is 12 in. and steady References to be provided during exam:
EOPs w/o entry conditions Based on the above conditions, what equipment is affected and what procedures are required?
[ref prv #2]
Explanation:
I I EOP bases I [ref #2]
I [ref #3]
Candidates will be provided a copy of Secondary Containment Control with no entry conditions. Additionally, we removed the 1 6 level from Table 13 (Max Safe Water Level), and removed components located within each area. Candidates are required to know which pumps are located within the four corner rooms, and what the max safe level is for these areas.
Therefore:
A is incorrect, Core Spray sys 1 pump ARE available, PCC is NOT entered.
B is the correct answer, Core Spray sys 2 pumps are NOT available, SCC IS entered.
C is incorrect, Containment Spray sys 1 pump ARE available, PCC is NOT entered.
Question Source Question Cognitive Level:
Bank I Modified Bank I [XI I New Memory or Fundamental
[XI Comprehension or Knowledge Analysis 10 CFR Part 55 Content:
I 55.41 I 55.43 I (b) (5)
Knowledge and Ability Reference Information 209001 Low Pressure Core Spray G 2.1.31 Importance Rating Core Spray Booster pump NZ03A breaker is racked out for repairs MN BRKR 1 D 86 LOCKOUT TRIP annunciator is received Two (2) minutes later, drywell pressure reaches 4 psig and is rising RPV water level is +55 in. TAF and lowering slowly RO SRO 3.9 A.
a Isolation Condensers and EMRVs.
Confirm NZOl A, NZOl D and NZ03D pumps are operating, maintain RPV pressure until water level reaches 0 in. TAF, then Emergency Depressurize.
Confirm NZO16, NZOI C and NZ03C pumps are operating, maintain RPV pressure until water level reaches 0 in. TAF, then Emergency Depressurize.
D.
C.
D.
ANSWER:
\\ A I T-2-e I RPV Control EOP Confirm NZOl A, NZOl D and NZ03D pumps are operating, then reduce pressure with Isolation Condensers and EMRVs.
Confirm NZOI B, NZOl C and NZOSC pumps are operating, then reduce pressure with REFERENCE(S):
Explanation:
References to be provided during exam:
On a loss of bus 1 D, the B and C Core Spray pumps lose power.
Additionally, with the priority booster pump NZ03A racked out, this will enable the backup booster pump NZ03D to start. In Level Restoration, after confirming low pressure injection subsystems running (2 of 3 between condensate, core spray 1 and core spray 2), if low pressure systems are capable of recovering level, direction is given in the pressure control leg via the last override statement to lower pressure as needed to allow the low pressure systems to inject. This is done prior to ever reaching TAF, and in this case, would be accomplished with ICs and EMRVs. It would not be appropriate to wait until reaching TAF then EDing, as this puts the vessel through an unneeded thermal transient. Therefore:
A is correct B is incorrect, based on wrong pumps available C is incorrect, based on not waiting to TAF for ED D is incorrect, based on wrong pumps and not waiting to TAF for ED EOPs with no entry conditions
[ref prv #2]
Learning Objective 10450
Question Source Bank Modified Bank New X
Question Cognitive Level:
Memory or Fundamental Comprehension or X
Knowledae Analvsis
Knowledge and Ability Reference Information 21 1000 Standby Liquid Control System A2.04 Importance Rating 0
0 0
0 PUMP ON light for system 2 illuminated (Panel 4F)
PUMP DISCH PRESS greater than Rx pressure (Panel 4F)
Squib continuity meter behind 4F reads 4.2 mA for system 2 RWCU system is in service RO SRO 3.4 Liquid poison is...
A. I Injecting, isolate the Reactor Water Cleanup system, IAW procedure 303 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 correct, control, or mitigate the consequences of those malfunctions or operations:
B. I NOT injecting, place LIQUID CONTROL keylock to the FIRE SYS 1 position, IAW SP-22 inadequate system flow C.
D' Injecting, verify Standby Liquid Control tank level lowering and monitor reactor power, IAW SP-22 NOT injecting, place LIQUID CONTROL keylock to OFF and then back to FIRE SYS 2 position, IAW SP-22 ANSWER:
) B REFERENCE(S):
] G-l-b, G-2-b I [ref #3]
Explanation:
A is incorrect, liquid poison is not injecting.
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.
D is incorrect, liquid poison is injecting but placing the keylock back to system 2 does not re-fire the squib valve References to be provided during exam:
None
[ref prv #2]
Learning 0 biective 10450 Question Source Question Cognitive Level:
~
~~
~
~
Bank 1 Modified Bank I
I New
[XI Memory or Fundamental Comprehension or
[XI Knowledge Analysis 10 CFR Part 55 Content:
I 55.41 1 55.43 I (b) (5)
-v-Knowledge and Ability Reference Information 21 8000 Automatic Depressurization G 2.1.28 Importance Svstem Ratina Question #
B.
C.
D.
Knowledge of the purpose and function of major system components and controls.
Question:
Following a plant transient, plant conditions are as follows:
operating as designed, initiate Standby Liquid Control, IAW SP-22 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 -
w/ATWS operating as designed, place EMRVs to MAN until RPV pressure is 920 psig, IAW RPV Control - w/ATWS 0
The reactor is at 8% power MSlVs are shut Reactor pressure is fluctuating between 1045 and 1070 psig Torus temperature is 75 deg. F Torus level is 146 in.
ANSWER:
ID REFERENCE(S):
The Automatic Depressurization System is...
EOP flowcharts I B-3-g 1 [ref #3]
References to be provided during exam:
B is incorrect, ADS working.and stabilizing pressure 1s wrong action for cycling EMRVs.
Explanation:
EOP flowcharts
[ref prv #2]
Learning Objective 10450 Question Source Question Cognitive Level:
Bank I Modified Bank I [XI I New Memory or Fundamental I [XI 1 Comprehension or I Knowledge
- - I Analysis 10 CFR Part 55 Content:
I 55.41 1 55.43 I (b) (5)
Knowledge and Ability Reference Information 21 2000 RPS A2.06 Importance Rating RO SRO 4.1 4.2 Given the following:
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 mitigate the consequences of those abnormal conditions or operations a
0 a
a a
a a
a e
a High Reactor Power The reactor was at 100% power when NS03B failed closed All remaining MSlVs closed on high flow NO control rods moved RPV level is being controlled -20 to 0 in. TAF Both Isolation Condensers are in service Two EMRVs are open, with a third being cycled to control pressure 800 to 1000 psig Torus temperature is 145 deg. F and rising at 2 deg. F per minute Torus level is 150 inches Boron is being injected SLC tank level is 1000 gal. and lowering A.
B.
Based upon the above, what actions are required?
Emergency Depressurize immediately.
Reduce RPV pressure within the next 8 minutes.
C.
D.
Reduce RPV pressure within the next 12 minutes.
Maintain present RPV pressure band until SLC tank level is 150 gallons, then commence a cooldown.
REFERENCE(S):
Explanation:
1 EOP bases I [ref #2]
I [ref #3]
The conditions listed above put the candidate 17 degrees away from the HCTL at 150 inches and 1000 psig. Since torus temp. cant be maintained below the HCTL, the RPV Control Pressure Control override directs maintaining RPV pressure below the HCTL. The candidate must determine that the most restrictive limit is at 1000 psig. Given the 2 deg. F per minute torus heatup, this gives approximately 8.5 minutes before reaching the HCTL at 1000 psig. Actions must be taken to depressurize before reaching the HCTL, therefore:
A is incorrect, as ED is not needed until the torus temperature and RPV pressure cannot be maintained below the HCTL.
B is correct C is incorrect, as the HCTL will be exceeded after approximately 8.5 minutes. The 12 minute time limit would be true for RPV pressure at 800
References to be provided during exam:
conditions EOP flow charts w/o entry c
[ref prv #2]
Learning 0 b jective 10450 Question Source Question Cognitive Level:
Bank I Modified Bank I
I New
[XI 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 201 002 Reactor Manual Control System A2.02 Importance Rating The plant is operating at 100% Power and the following conditions exist:
6 control rods are valved out of service at 00 due to HCU problems ROD DRIFT alarm is received and rod 10-35 moves out to position 48 without operator action All attempts to insert the control rod are unsuccessful Investigation reveals NO known cause for the failure 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 correct, control, or mitigate the consequences of those malfunctions or operations Rod drift alarm A.
B.
C.
D.
associated with this spec. Therefore:
A is correct.
Explanation:
Commence an uninterrupted plant shutdown immediately Place the plant in a shutdown condition within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> Place the plant in a cold shutdown condition within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> Place the Dlant in a shutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> ANSWER:
/ A REF E R EN CE( S):
Tech Specs I ABN-6 I [ref #3]
References to be provided during exam:
Tech Specs
[ref prv #2]
T.S. 3.2.B.4 Learning Objective 10447 Question Source Question Cognitive Level:
Bank I [XI I Modified Bank I
I New Knowledge Analysis Memory or Fundamental Comprehension or
[XI 10 CFR Part 55 Content:
I 55.41 I 55.43 I (b) (2)
I
Knowledge and Ability Reference Information RO 241 000 Reactor/Turbine Pressure G2.4.21 Importance Regulating System Rating SRO 4.3 Given the following:
ANSWER:
IC REFERENCE(S):
0 Reactor power is 40%
0 0
A plant startup is in progress Power ascension is limited to 10% per hour Reactor pressure is being maintained at 1020 psig EPR servo percent stroke is 40%
MPR servo percent stroke is 32%
31 5.5 I GE SIL 614 I [ref #3]
Reactor pressure takes a step jump to 1024 psig, and the CRO reports the following indications:
0 EPR servo percent stroke is 0%
MPR servo percent stroke is 40%
Explanation:
Based upon the above, the direction to the CRO is to (1 1 has failed. As Unit Supervisor, your (2)
With the stated plant conditions, these indicate the EPR has failed. With power between 25% and 90% and only one pressure regulator, either raise power above 90% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or reduce power below 25% within the following 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Since the power ascension limit is 10% per hour, it is not possible to raise power above 90% within a two hour time frame. Therefore, power must be reduced below 25% within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
A is incorrect, as power ascension in this condition is not allowe B is incorrect, as MPR did not fail, and power ascension in this condition is not allowed C is correct D is incorrect, as the EPR failed
References to be provided during exam:
None
[ref prv #2]
Learning Objective 01 196,01200 Question Source Question Cognitive Level:
Bank I Modified Bank I
1 New X
Memory or Fundamental I
I Comprehension or X
I Knowledge I Analysis
-v Knowledge and Ability Reference Information 2.1 Conduct of operations 2.1.12 Importance Rating RO SRO 2.9 4.0 Weekly surveillance results on the B Station Battery are as follows:
Overall battery voltage while on Float Charge: 128.5 volts Pilot cell specific gravity (temperature corrected):
1.1 75 Tech Specs require...
Pilot cell voltage while on Float Charge:
2.1 5 volts 634.2.002 T.S. 3.7.A.4; 4.7.B.1.d REFERENCE(S):
A. I NO additional action 0P-0c-100 B. I the Dlant to be in SHUTDOWN within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> Learn i ng Objective C. I the Dlant to be in COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 10451 Question Source Question Cognitive Level:
I A is incorrect readings are out of spec Bank 1 Modified Bank I I New X
Memory or Fundamental Comprehension or X
Knowledge Analysis B is correct C is incorrect for weekly surveillances Explanation:
I D is incorrect for s/g cl.190 (would be correct for 21.1 90 but 51.205)
References to be I T.S. section 4.7
Knowledge and Ability Reference Information 2.1 Conduct of operations 2.1.23 Importance Rating Review the attached data sheets and:
(2) determine required actions determine status of Isolation Condensers Am B.
Dm (1)
(2)
No actions required.
(1 )
(2)
(1)
(2)
(1 )
(2)
OD Both Isolation Condensers are operable.
Both Isolation Condensers are inoperable.
Place reactor in cold shutdown condition.
A Isolation Condenser is operable; B Isolation Condenser is inoperable.
Operation may continue for up to 7 days.
A Isolation Condenser is inoperable; B Isolation Condenser is operable.
ANSWER:
Explanation:
~
I ation may continue for up to 7 days.
References to be provided during exam:
I I 609.4.001 I Tech Specs 3.8 Valve V-14-30 (IC A) is out of acceptable range but within limiting value range making IC A degraded but operable. V-14-33 (IC B) is out of acceptable range and outside of limiting value range making IC B inoperable. T.S. 3.8 states that with one IC inoperable the reactor may remain in operation not to exceed 7 days. Therefore:
A is incorrect B is incorrect C is correct D is incorrect Tech Spec sectio completed attachment 609.4-(page E2-3) with Acceptance Criteria (page 20)
&a 001 -1 (page El -2) and -2 Learning 0 bjective 08653 Question Source Question Cognitive Level:
Bank I Modified Bank I I New X
Memory or Fundamental Comprehension or X
Knowledge Analysis
Knowledge and Ability Reference Information I G 2.2.29 I Importance Question# I S21 Examination Outline Cross-reference Level 1 SRO I Tier#
13 I Grow # I CAT 2 RO SRO 3.8 A.
B.
I Rating Knowledge of SRO fuel handling responsibilities.
A Fuel Assembly is discovered to be mis-located in the core after performing the following fuel move A Fuel Assemblv is discovered to be mis-located in the went fuel ~ o o l C.
D.
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 the grapple I D is incorrect, not an error until bridge is moved north/south..
References to be provided I None I [ref prv #21 ANSWER:
I A REFERENCE(S):
Procedure 205 I [ref #2]
I [ref #3]
Learning Objective 1129 Question Source Question Cognitive Level:
Bank I [XI I Modified Bank I
I New Knowledge Analysis Memory or Fundamental Comprehension or
[XI 10 CFR Part 55 Content:
I 55.41 I 55.43 I (b) (7)
L-Knowledge and Ability Reference Information RO G 2.2.22 Importance Rating Question #
1 S22 SRO 4.1 Examination Outline Cross-reference Level I SRO I Tier #
I 3 I GrouD# I CAT2 References to be provided during exam:
None
[ref prv #2]
Question:
Given the following conditions:
Learning Objective 0
Reactor is at 100% power MCPR is determined to be 1.08 10451 What action is required IAW Technical Specifications?
Question Source Question Cognitive Level:
A.
1 The reactor shall be shutdown immediately Bank 1 Modified Bank I [XI 1 New Knowledge Analysis Memory or Fundamental Comprehension or
[XI B. 1 The reactor shall be placed in cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> 10 CFR Part 55 Content:
C. 1 Return MCPR within limits in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be shutdown in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 55.43 (b) (2)
(letter) 55.41 num D. I Return MCPR within limits in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in cold shutdown in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> ANSWER:
/ A T.S. 2.1, sect. 6 I [ref #2]
I [ref #3]
A is correct, for any safety limit violation.
REFERENCE(S):
Explanation:
B is incorrect, plausible for violation of LCO but not for safety limit.
C is incorrect, plausible for violation of steady state LCO, but cold shutdown required.
D is incorrect, plausible for violation of steady state LCO.
L--
Knowledge and Ability Reference Information 2.3 Radiation Control 2.3.1 Importance Rating 0
0 0
Vibration readings are being taken at the marked spot on the attached survey map The job is expected to take 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Your year-to-date dose is 1,750 mrem TEDE RO SRO 2.6 3.0 If you were to stay in the area for the entire 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, answer the following questions.
A.
B-
- c.
D-(1)
(2)
What is your expected dose for this job?
Besides the Radiation Protection Manager, whose permission is required to authorize this job?
(1) 275mrem (2)
No additional permission required (1) 275mrem (2)
Operations Director (1) 350 mrem (2)
Shift Manager (1) 350 mrem (2)
Plant Manager ANSWER:
I C REFERENCE(S):
RP-AA-203, Exposure Control and Authorization # sU.d\\fb!W
- I---
References to be provided during exam:
Survey map Learning Objective 18, 25 from NGET Rad Worker Training Question Source Question Cognitive Bank I Modified Bank I 1 New X
Memory or Fundamental I I Comprehension or X
Knowledge and Ability Reference Information G 2.4.38 Importance Rating RO SRO 4.0 At 081 0:
0 0
0 0
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 EDG 2 fails to start C.
D.
At 081 3:
0 EDG 2 fails to emergency start from the control room 0840 0843 At 0828:
0 EDG 2 is started locally and it output breaker is closed and it supplies power to its respective bus ANSWER:
I C REFERENCE(S):
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?
EP-OC-1010 I [ref #2]
I [ref #3]
References to be provided EP-OC-1010 during exam:
[ref prv #2]
Question Source Question Cognitive Level:
L-
~~
Bank I Modified Bank I
I New
[XI 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 G 2.4.41 Importance Ratina Knowledge of the emergency action level thresholds and classifications RO SRO 2.3
4.1 Question
Given the following conditions:
A.
- 6.
0 0
0 0
0 The plant is in a refueling outage A refueling accident has occurred The refuel floor has been evacuated B9 and C9 radiation monitors are alarming SGTS has initiated and Reactor Building HVAC has tripped Unusual Event Alert 30 minutes later, the following conditions exist:
References to be provided during exam:
0 High Range Stack RAGEMS reads 1.O vCi/cc NO field monitoring reports have been received EP-OC-1010 Based upon these conditions, classify the event.
Learning Obiective 08908 C. I Site Area Emergency D. I General Emergency ANSWER:
I C I
Explanation:
I Knowledge I Question Cognitive Level: I Memory or Fundamental I
I Comprehension or I x I I Analysis 10 CFR Part 55 Content:
I 55.41 I 55.43 I (b)(5)