ML21041A294

Original Questions for Modified Written Exam Questions

ML21041A294
Person / Time
Site:	Ginna
Issue date:	10/03/2019
From:	Exelon Generation Co
To:	Thomas Setzer Operations Branch I
Shared Package
ML18347A730	List: ML18353A608 ML19193A078 ML20024E249 ML20024E699 ML20024E750 ML20024E820 ML20041E177 ML21041A294
References
EPID L-2019-OLL-0039
Download: ML21041A294 (26)

Text

Generator Capability Curve...

!Question 1 ID: 1814856

<<Plant conditions occurred as follows:

OR-\\(;:. f,J I-\\ L While at rated power, there was a disturbance on the electrical power grid which required the unit to perform a load reduction The CO reports that Main Generator MVARs have gone from 150 MVARs OUT to 40 MVARs IN and rising on the MCB Generator loading is 500 MWe Using the provided Generator Capability Table, if current conditions continue:

1) Which Megavar limit will be met FIRST?

AND

2) In this condition, the grid is more ______,>>

A.

<<1)-159 MVARs

2) inductive>>

B.

<<1) 325 MVARs

2) inductive>>

C.

<<1) -159 MVARs

2) capacitive>>

D.

<<1) 325 MVARs

2) capacitive>>

!Answer C

Answer Explanation A. <<<<<<<<<<<<INCORRECT. Plausible since the first part is correct and the candidate may believe that with the Main Generator taking MVARs IN that an inductive state exists.

B. INCORRECT. Plausible since the Megavars limit is correct for the generator loading in an inductive (overexcited) state and the candidate may believe that voltage is leading current when a capacitive state exists.

C. CORRECT. With MVARs coming into the Main Generator, a capacitive state exists on the electrical grid and the generator will be underexcited. In accordance with 0-6.9, Attachments 16 and 17, the lower half of the curve is used (underexcited) and the limit is -159 Megavars.

D. INCORRECT. Plausible since the Megavars limit is correct for the generator loading in an inductive (overexcited) state and the second part is correct.

Question ID: 1814856

Generator Capability Curve...

Question Preview Question Information Topic

<<Generator Capability Curve>>

User ID I system 10 1<<1814856>>

Project

<<GN-OPS>>

Status

<<Active>>

I Point Value 1 <<1.00>>

ITlme(mln) l<<O>>

Open or Closed Reference

<<CLOSED>>

Operator Type-Cognitive Level

<<job-MEMORY>>

Operator Discipline

<<LO-I>>

<<References Provided None KIA Justification SRO-Only Justification Additional Information KIA APE 077, Generator Voltage and Electric Grid Disturbances, AA2.03 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbance: Generator current outside the capability curve 0-6.9, Attachment 16 to be provided to students>>

KIA Reference(s)

Question not linked to K/As Learning Objective(s)

^Describe indications and/or alarms associated with the Main Generation system that would cause entry into an:

a.

Annunciator Response Procedure

b.

Abnormal Procedure c.

Emergency Procedure User (Sys) ID R0501C 1.11 (1306960)

Cross Reference Links None Question ID: 1814856

EOP procedural knowledge...

I Question 1 ID: 1711453

<<Given the following plant conditions:

The plant has experienced a LOCA Qu6s-r*o

IR' c)\\C:tl,JAL The operators have taken appropriate action in accordance with E-0, Reactor Trip or Safety Injection, and E-1, Loss of Reactor or Secondary Coolant The ECCS is now operating in the cold leg recirculation mode RCS pressure is stable at approximately 150 psig with 300°F on core exit T/Cs SIG pressure is 300 psig Which ONE of the following describes the method of core decay heat removal?>>

A <<Heat transfer between the RCS and the S/Gs due to natural circulation flow>>

B.

<<Injection water being boiled off in the core and steam exhausting out the break>>

c.

<<Heat transfer between the RCS and the S/Gs due to forced circulation flow>>

D.

<<The injection of water from the recirculation sump and the removal of steam/water out of the break>>

!Answer D

Answer Explanation

<<Justification a,c. SIG heat removal not indicated because T SA r RCS < T SA r SIG

b. Sufficient subcoo/ing exists to prevent core boiling.

d. Correct. Per ERG Background - Requires trainee to evaluate core conditions to determine correct answer.>>

Question ID: 1711453

EOP procedural knowledge...

Question Information Topic

<<EOP procedural knowledge>>

User ID

<<POTEET>>

Project

<<GN-OPS>>

Status

<<Active>>

I Point Value Open or Closed Reference

<<OPEN>>

Operator Type..cognltlve Level

<<job-HIGH>>

Operator Dlsclpllne

<<program-ct>>

<<References Provided KIA Justification SRO-Only Justification Additional Information KIA Reference(s)

Question not linked to K/As Learning Objective(s)

Question not linked to a Learning Objective Cross Reference Links Table: TRAINING-QUESTION-AN-Level of Dlfflculty I <<1.00>>

Level 3: Moderately discriminating. Expected miss rate of 20% - 30%

Table: TRAINING-QUESTION-AN-Cognitive Level 3 Higher Cognitive Level Application/Analysis/Problem Solving Question ID: 1711453 I system ID ITlme(mln)

Question Preview 1<<1711453>>

l<<O>>

GDT operation/ accidental release...

!Question 1 ID: 1712411

<<Given the following conditions:

Plant is at 100% power

'A' Gas Decay Tank (GOT) is in service

'A' Gas Decay Tank pressure starts, and continues, to rise If the pressure rise is not stopped, which of the following will occur?

'A' GOT Relief

'A' GOT Rupture R-10A, CNMT IODINE Trends Lifts Disk Breaks UP A.

<<142 psig 150 psig YES B.

<<142 psig 150 psig NO C.

<<150 psig 142 psig NO D.

<<150 psig 142 psig YES

!Answer C

Answer Explanation OvE-S,t o.J fl: 2. 3 R-108, PLANT VENT IODINE, Trends UP NO YES YES NO A

<<Incorrect. Plausible because the examinee will be required to recall from system knowledge that GOT relief and rupture disk setpoints (wrong relief setpoints). The examinee will have to recall that rupture disc will break before the relief opens. The examinee should recognize that rad monitoring trends will rise, but not in CNMT R-10A) for this situation as the release will be to the Aux bldg. causing a rise on R-108.

B.

Incorrect. Plausible because the examinee will be required to recall from system knowledge that GOT relief and rupture disk setpoints (wrong relief setpoints). The examinee will have to recall that rupture disc will break before the relief opens. The examinee should recognize that rad monitoring trends will rise, but not in CNMT for this situation as the release will be to the Aux bldg. causing a rise on R-1 OB.

Question ID: 1712411

GDT operation/ accidental release...

Question Preview C.

CORRECT. Plausible because the examinee will be required to recall from system knowledge that GOT relief and rupture disk setpoints (correct relief setpoints). The examinee will have to recall that rupture disc will break before the relief opens. The examinee should recognize that rad monitoring trends will rise, but not in CNMT (R-10A) for this situation as the release will be to the Aux bldg. causing a rise on R-108.

0.

Incorrect. Plausible because the examinee will be required to recall from system knowledge that GOT relief and rupture disk setpoints. The examinee will have to recall that rupture disc will break before the relief opens. The examinee should recognize that rad monitoring trends will rise, but not in CNMT (R-10A) for this situation as the release will be to the Aux bldg. causing a rise on R-1 OB.>>

Question Information Topic

<<GDT operation/ accidental release>>

User ID I system ID 1<<1712411>>

Project

<<GN-OPS>>

Status

<<Active>>

I Point Value I <<1.00>>

I Time (min) l<<O>>

Open or Closed Reference

<<CLOSED>>

Operator Type-Cognitive Level

<<job-MEMORY>>

Operator Discipline

<<LO-I>>

10CFR55 Content

<<CFR: 41.11 Purpose and operation of radiation monitoring systems, including alarms and survey equipment.>>

<<References Provided None KIA Justification SRO-Only Justification Additional Information KIA APE 060 AK2.02 Knowledge of the interrelations between the accidental Gaseous Radwaste Release and the following:

Auxiliary Building Ventilation system Tier 1, Group 2 10 CFR Part 55 Content: 55.41 (11) 55.43 LP R3801C, Obj. 7.02 Question ID: 1712411

USED ON 2008 GINNAAUDIT EXAM (Q.18) consider putting dlstractors in table form below on actual exam page

'A' GDT Relief Lifts A.

142 psig B.

142 psig C.

150 psig D.

150 psig KIA Reference(s)

Question not linked to K/As Learning Objective(s)

'A' GDT Rupture Disk Breaks 150 psig 150 psig 142 psig 142 psig Question not linked to a Learning Objective Cross Reference Links None Question ID: 1712411 R-10A, CNMT IODINE Trends UP YES NO NO YES Question Preview R-108, PLANT VENT IODINE, Trends UP NO YES YES NO

Pressurizer Relief Tank purpose of level band...

!Question 1 ID: 1704845 Ove.s-.,o,,l -Ct3'-t olt \\1,.lAl-

<<Which of the following describes the adverse effects of NOT maintaining the Pressurizer Relief Tank (PRT) within design level band?>>

A

<<If the level is too high, the tank will overflow to CNMT sump causing possible false indication of RCS leakage to CNMT.>>

B.

<<If the level is too low the radioactive gases that leak from the top of the PRZR would not be adequately scrubbed, thus causing subsequent elevated gaseous activity levels inside CNMT.>>

C.

<<If the level is too high, the sparger pipe will be too far underwater rendering the cooling effect of makeup water ineffective.>>

D.

<<If the level is too low, there would be insufficient water volume to absorb and condense a design discharge of PRZR safety leading to possible over temperature and overpressure of the PRT.>>

!Answer D

Answer Explanation

<<If the level is too low, there would be insufficient water volume to absorb and condense a design discharge of PRZR safety leading to possible over temperature and overpressure of the PRT.>>

Question Information Topic

<<Pressurizer Relief Tank purpose of level band>>

User ID

<<63494>>

I system ID 1<<1704845>>

Project

<<GN-OPS>>

Status

<<Active>>

I Point Value 1 <<1.00>>

ITlme(mln) l<<O>>

Open or Closed Reference Operator Type-Cognitive Level

<<job-cog>>

Operator Discipline

<<program-ct>>

<<References Provided KIA Justification SRO-Only Justification Question ID: 1704845

Pressurizer Relief Tank purpose of level band...

Additional Information I KIA Reference(s)

Question not linked to K/As Learning Objective(s) 1.

9Describe the design features that enable the Pressurizer and Pressurizer Relief Tank System to perform their functions.

User (Sys) ID R1401C 1.04 (1301041)

Question Preview 2.

Given a specific fundamental principle, performance test, limits and/or precautions for the Pressurizer and Pressurizer Relief Tank System or component, describe the reason/basis and the effect on the operations of the system or component User(Sys) ID R1401C 1.09 (1307144)

Cross Reference Links Table: TRAINING-QUESTION-GN-OPS-General Data Ginna Initial Question ID: 1704845

A precaution in P-4 gives maximum CCW flow require...

ID: 1704383 Qvc*no...\\ Jt"3t DR.,\\e,.1 NP.'-

<<A precaution in P-4 gives maximum CCW flow requirements for CCW pump and heat exchanger combinations.

Which one of the following gives the basis for this maximum flow?>>

A.

<<Pump run out concerns.>>

B.

<<NPSH concerns>>

C.

<<Piping stress concerns at major pipe turns/elbows>>

D.

<<CCW heat exchanger damage due to flow induced vibration.>>

jAnswer D

Answer Explanation

<<CCW heat exchanger damage due to flow induced vibration.>>

Question Information Topic

<<A precaution in P-4 gives maximum CCW flow requirements for CCW pump and heat exchanger combinations>>

User ID

<<C008.0072>>

jsystem ID 1<<1704383>>

Project

<<GN-OPS>>

Status

<<Active>>

j Point Value 1 <<1.00>>

jTime(mln) j<<O>>

Open or Closed Reference Operator Type-Cognitive Level

<<job-cog>>

Operator Discipline

<<program-ct>>

<<References Provided KIA Justification SRO-Only Justification Additional Information Question ID: 1704383

A precaution in P-4 gives maximum CCW flow require...

KIA Reference(s)

Question not linked to K/As Learning Objective(s)

Question Preview 1.

ABe able to explain and apply the CCW system limits and precautions of P-4, "Precautions, Limitations and Setpoints Auxiliary Coolant System".

User (Sys) ID R2801C 5.01 (1304220) 2.

AGiven a specific fundamental principle, performance test, limits and/or precautions for the Component Cooling Water System or component, describe the reason/basis and the effect on the operations of the system or component.

User (Sys) ID R2801C 1.09 (1307323)

Cross Reference Links Table: TRAINING-QUESTION-GN-OPS-General Data Ginna Initial Question ID: 1704383

!Question 1 ID:1704671 c..?ve-r I o.,J #-3 8 D \\G:tl

L

<<Which one of the following lists describes the major plant responses to a loss of any single instrument bus?

Assume no corrective action is taken by the operator and plant at 100% power normal lineups on all system.>>

A.

<<1) Average Tavg - Tref deviation rod stop 2) Turbine Load Limit runback 3) Delta T and rod stop single channel alert>>

B.

<<1) Average Tavg - Tavg deviation rod stop 2) Dropped rod rod stop 3) Delta T and rod stop single channel alert>>

C.

<<1) Average Tavg - Tref deviation rod stop 2) Dropped rod rod stop 3) Delta T and rod stop single channel alert>>

D.

<<1) Average Tavg - Tavg deviation rod stop 2) Letdown isolation 3) Turbine Load Limit runback>>

!Answer B

Answer Explanation

<<1) Average Tavg - Tavg deviation rod stop 2) Dropped rod rod stop 3) Delta T and rod stop single channel alert>>

Question Information Topic

<<Which one of the following lists describes the major plant responses to a loss of any single instrum>>

User ID

<<C063.0020>>

I system ID 1<<1704671>>

Project

<<GN-OPS>>

Status

<<Active>>

I Point Value 1 <<1.00>>

I rime (min) l<<O>>

Open or Closed Reference

<<OPEN>>

Operator Type-Cognitive Level

<<SRO-cog>>

Operator Discipline

<<LO-ct>>

<<References -Provided KIA Justification Question ID: 1704671

Which one of the following lists describes the maj...

SRO-Only Justification Additional Information KIA Reference(s)

Question not linked to K/As Learning Objective(s)

Question Preview 1.

nDemonstrate the ability to predict and/or monitor the effects of operation of RPS circuit breakers.

User (Sys) ID R3501 C 6.15 (1304298)

2.

nGiven the loss of any instrument bus, predict the common effects on continued plant operation.

User (Sys) ID RIC12C 1.03 (1305050) 3.

nGiven the loss of a specific instrument bus (A, 8, C, D) predict the effect on continued plant operation.

User(Sys) ID RIC12C 1.04 (1305051) 4.

nPredict the effect(s) of a loss or malfunction of the following component(s) and/or instrumentation on the Reactor Protection System:

a.

120 VAC Electrical Distribution System

b.

125 voe Electrical Distribution System c.

Bistables and Bistable Test Equipment d.

Input (Instrument or Process) Loop Components e.

Logic Loop Components f.

Rod Stop (Block) Circuits g.

Permissive Circuits User(Sys) ID R3501C 1.10 (1307542) 5.

nPredict the effect that a loss or malfunction in the 120 VAC Instrument Bus System will have on related plant system(s) and/or plant operations.

a.

Rod Control System.

b.

Nuclear Instrumentation System.

c.

Rod Insertion Limits (RIL).

d.

Pressurizer Pressure Control System.

e.

Main Turbine EHC System.

f.

Heater Drain System.

g.

Steam Dump System.

h.

Chemical and Volume Control System (CVCS).

i.

Reactor Protection System.

j.

Condensate System.

k.

MCB Controllers.

I.

Pressurizer Level Control System.

m.

Main Turbine Auxiliaries.

User (Sys) ID RIC12C 1.06 (1308212) 6.

nDemonstrate the ability to predict and/or monitor the effects of operation of RPS circuit breakers.

User (Sys) ID R3501C 6.15 (1310119)

Cross Reference Links Table: TRAINING-QUESTION-GN-OPS-General Data Ginna Initial Question ID: 1704671

Knowledge of the effect that a loss or malfunction...

!Question 1 ID: 2132300

<<Given the following plant conditions:

4u6ST"JorJ lt-7 O\\G!tt,J AL An accident has resulted in automatic SI and Containment Spray actuation CNMT pressure is 30 psig and slowly lowering SI has NOT yet been reset Bus 16 NORMAL Supply breaker has just tripped DIG B output breaker closed and re-energized Bus 16 WHICH ONE of the following describes the response of SI pump B and CS pump B?>>

A.

<<Both pumps will automatically restart>>

B.

<<Both pumps must be manually restarted using the individual pump breaker controls>>

C.

<<SI pump B will automatically restart, but CS pump B must be started manually using its individual pump breaker control>>

D.

<<CS pump B will automatically restart, but SI pump B must be manually started using its individual pump breaker control>>

!Answer A

Answer Explanation

<<A CORRECT. Following the SI actuation, the subsequent UV condition (112 +

112 UV sensors) on Bus 16 trips SI pump B & C breakers, CRFs B & C, MDAFW pump B, and RHR pump B. Since SI has not been reset, the actuation signal is still present and when the DIG B re-energizes Bus 16 (Sl+UV sequence), SI pump B breaker recloses and CS pump B (whose breaker was never stripped and does not open on UV), is re-energized.

Both components restart automatically with no actions required.

B.

Incorrect. Plausible if the candidate does not recognize that the SI signal is still present nor recognize that the CS pump does not have UV protection.

Question ID: 2132300

Knowledge of the effect that a loss or malfunction...

Question Preview C.

Incorrect. Plausible because part 1 is correct and if, in part 2, the candidate fails to recognize that the CS pump does not have UV protection and does not need to be manually restarted.

D.

Incorrect. Plausible because part 1 is correct and part 2 is plausible if the candidate fails to recognize that the SI signal has not been reset and ECCS components will restart.

Question Information Topic

<<Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the fo>>

User ID

<<SF6 062 K3.01 >>

!system ID 1<<2132300>>

Project

<<GN-OPS>>

Status

<<Active>>

I Point Value 1 <<1.00>>

ITlme(mln) l<<O>>

Open or Closed Reference

<<CLOSED>>

Operator Type-Cognitive Level

<<RO-MEMORY>>

Operator Discipline

<<ILT>>

<<References Provided NONE Knowledge of the effect that a loss or KIA Justification malfunction of the ac distribution system will KIA Reference(s)

GNA-SF6.062.K3 Knowledge and Abilities have on the followin SRO-Only Justification NIA Add.ti I I 2.

ti 33013-1353, Sheets 5 & 8 1 ona n,orrna on p_12 R0701C 1.06 Last NRC Exam: 2014 Ginna Bank 18470 I Safety Function I Tier I Group I RO Imp:

lsRo Imp:

Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: (CFR:

41.7 / 45.6)

Question ID: 2132300

Learning Objective(s)

Question not linked to a Learning Objective Cross Reference Links None Question ID: 2132300 Question Preview

Diagnose impact of loss of Bus 13 on Instrument Ai...

jauestion 1

<<The following plant conditions exist:

100% power ID: 1704742

'C' Instrument Air compressor is running All major control systems in AUTO Service and Instrument Air are aligned normally Bus 13 deenergizes Q c.J ST10..J -#t S Lf OP-..(c,.{,JAL Without Operator action, which of the following is the Air Compressor that is expected to be running?>>

A.

<<Service Air Compressor>>

B.

<<'A' Instrument Air Compressor>>

C.

<<'B' Instrument Air Compressor>>

D.

<<'C' Instrument Air Compressor>>

jAnswer D

Answer Explanation

<<'C' Instrument Air Compressor>>

Question Information Topic

<<Diagnose impact of loss of Bus 13 on Instrument Air system>>

I system ID User ID

<<8078.0016>>

Project

<<GN-OPS>>

Status

<<Active>>

I Point Value 1 <<1.00>>

ITtme(mln)

Open or Closed Reference Operator Type-Cognitive Level

<<job-MEMORY>>

Operator Discipline

<<program-R>>

• .::<References Provided KIA Justification

- +

SRO-Only Justification Question ID: 1704742 1<<1704742>>

l<<O>>

Diagnose impact of loss of Bus 13 on Instrument Ai...

Additional Information I KIA GNA-SF8.078.K6.01>>

KIA Reference(s)

Question not linked to K/As Learning Objective(s) 1.

PGiven a set of plant conditions and a failure of one of the following major components in the Instrument/Service Air system, predict how the system will respond.

a. Instrument Air Compressor A and B

b. Service Air Compressor

c. Air Dryer and Filters A and B

d. Service Air Header

e. Instrument Air Header

f. 'C' Instrument Air Compressor

g. 'C' Compressor Dryer Unit User (Sys) ID R4701C 5.01 (1302384)

Question Preview 2.

PPredict the effect(s) of a loss or malfunction of the following component(s) and/or instrumentation on the Instrument and Service Air System a.

Air Compressors b.

Air Dryers C.

Air Filters User (Sys) ID R4701C 1.10 (1307656) 3.

-$-when given a task associated with the Secondary Operator Certification Guide, the operator will be able to perform the task with appropriate system knowledge IAW the Standard provided in the Certification Guide User (Sys) ID N/A (1311703)

Cross Reference Links Table: TRAINING-QUESTION-GN-OPS-General Data Continuing Ginna Question ID: 1704742

Identify the electric power supplies to the follow...

I Question 1 ID: 2058945 QJS1'JoJ #S7 0 'R. l6tl,J AL-

<<The plant is operating normally at 100%, with the electric plant in a Normal 50/50 lineup, when the normal feeder breaker to 480V Bus 14 trips on a fault. Because of the fault, the A Emergency Diesel Generator starts, but the Emergency Feeder Breaker to Bus 14 does NOT close. What is the current status of the Pressurizer Proportional Heaters?>>

A

<<deenergized due to loss of power.>>

B.

<<fully energized because of the loss of power to pressure controller 431 K.>>

C.

<<partially energized, controlling RCS Pressure in band.>>

D.

<<partially energized, as pressure controller 431 K has failed "as-is" upon the loss of power.>>

jAnswer A

Answer Explanation

<<The proportional heaters are powered from 480V Bus 14. Since the normal and emergency feeder breakers to Bus 14 are open, the heaters are deenergized.

Ref. UFSAR, P-2, 0-7>>

Question Information

<<Identify the electric power supplies to the following system components:

Topic Pressure instruments.

Le>>

User ID

<<EO-PZR-1>>

I system 10 1<<2058945>>

Project

<<GN-OPS>>

Status

<<Active>>

I Point Value 1 <<1.00>>

ITlme(mln) l<<O>>

Open or Closed Reference

<<CLOSED>>

Operator Type-Cognitive Level

<<EO-High>>

Operator Discipline

<<EO-CT>>

Question ID: 2058945

Identify the electric power supplies to the follow...

<<References Provided None KIA Justification N/A SRO:;only Justification NIA Additional Information None KIA Reference(s)

Question not linked to K/As Learning Objective(s) 2Identify the electric power supplies to the following system components:

a.

Pressure instruments.

b.

Level instruments.

c.

Pressurizer heaters.

User (Sys) ID R1901C 1.05 (1307184)

Cross Reference Links None Question ID: 2058945 Question Preview

Mitigating actions of AP-CVCS.3...

!Question 1

<<Given the following:

ID: 1713804

'A' and 'C' charging pumps are RUNNING A-4, REGEN HX LETDOWN OUT HI TEMP 395°F, is received The crew initially entered AP-CVCS. 1, eves LEAK EO reports the relief valves on the running charging pumps are lifting au, sno,J It:

o lt_\\ fst1..JAL.

Charging flow indicator Fl-128 has been steadily LOWERING and now reads O gprn F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5, is received PRZR level is LOWERING slowly Which ONE of the following states...

1) The appropriate procedure to provide mitigating actions, AND

2) The final plant status (disregard any long-term recovery actions)?>>

A.

<<1) AP-CVCS.3, LOSS OF ALL CHARGING FLOW

2) Reactor shutdown with Tcold ~535°F, RCS pressure ~1400 psig>>

B.

<<1) AP-CVCS.3, LOSS OF ALL CHARGING FLOW

2) Reactor shutdown with Tavg ~547°F, RCS pressure ~2235 psig>>

C.

<<1) AP-RCS.1, REACTOR COOLANT LEAK

2) Reactor shutdown with Tavg ~547°F, RCS pressure ~2235 psig>>

D.

<<1) AP-RCS.1, REACTOR COOLANT LEAK

2) Reactor shutdown with Tcold ~455°F, RCS pressure ~1400 psig>>

!Answer A

Answer Explanation A

<<CORRECT. The conditions provided in the question are sufficient for the candidate to recognize that normal charging flow is not available and requires a transition to AP-CVCS.3, LOSS OF ALL CHARGING. The end-point of AP-CVCS.3 is maintaining Tcold ~535°F and RCS pressure ~1400 psig.

B.

Incorrect. Plausible because the first part is correct, and the second part identifies conditions following a plant shutdown. Incorrect because the end point of AP-CVCS.3 is maintaining Tcold ~ 535°F and RCS Pressure ~1400 psig.

C.

Incorrect. Plausible because alarm F-4 is one of the symptoms of AP-RCS.1, and AP-RCS.1 directs plant shutdown per 0-2.1. This would result in no-load temperature and pressure.

Question ID: 1713804

Mitigating actions of AP.-CYCS.3...

Question Preview D.

Incorrect. Plausible because alarm F-4 is one of the symptoms of AP-RCS.1. The candidate may confuse the cooldown.the-requirement with the one from AP-SG.1, which is Tcold at 455°F. The 1400 psig is the pressure that would be required per AP-CVCS.3. Incorrect because the correct procedure to use is AP-CVCS.3, and the end-point of AP-CVCS.3 is maintaining Tcold ~535°F and ROS p;;essure ~ 1400 psig.>>

Question Information Topic

<<Mitigating' acfion&-bf AP-CVCS.$)(>

User ID

<<2012 IL T NRC EXAM>>

<<GNlopw,;>*' *.;.

/'"','(".* f I

Project Status

<<Active>>

• I Point Value Open or Closed Reference

<<CLOSED>>

Operator Type-Cogn_itlve Le-I *,

<<RO-HIGH>>

Operator Discipline

<<LO-I>>

KIA 004 2.1.23 eves

• * !

• r: r <<Referenc,s Provided

....:"', v"",.... ;

KIA Justification SRO-Only Justification

._*.Cddltional Information Conduct of Operations i.

I system ID 1<<1713804>>

1 <<1.00>>

lrtme(mln) l<<O>>

None Not applicable Ability to perform specific system and integrated plant procedures during all modes of a plant operation RAP31C>>

KIA Reference(s)

Question not linked to K/As Learning Objective(s) xGiven a set of plant and equipment conditions, evaluate the conditions to determine the applicable procedure, and from the procedure determine the appropriate EXPECTED ACTIONS or RESPONSE NOT OBTAINED instructions to implement in AP-CVCS.3, Loss of All Charging Flow.

User (Sys) ID RAP31C 2.01 (1303441)

Cross Reference Links None Question ID: 1713804