ML040490429

May 2003 Exam 50-348/2003-301 Final RO Written Exam Revised Per Comments/Appeals

ML040490429
Person / Time
Site:	Farley
Issue date:	07/03/2003
From:	Ernstes M Operator Licensing and Human Performance Branch
To:	Beasley J Southern Nuclear Operating Co
References
50-348/03-301, 50-364/03-301 50-348/03-301, 50-364/03-301
Download: ML040490429 (77)

See also: IR 05000348/2003301

Text

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U.S. Nuelear Regulatory Commission

S ite -S pec ific

RO Written Examination

I Name:

Use the answer sheets provided to document your answers. Staple this cover sheet on tog

of the answer sheets. To pass the examination you must achieve a final grade of at least

80.00 percent. Examination papers will be collected six hours after the examination starts.

Applicant Certification

All work done on this examinatiom is my Q W ~ . I have neither given nor received aid.

Examination Value

Points

Applicant's Grade

i_

1.

The plant is operating at 95% steady-sfate power. The crew has been requested to

perform an RCS leakage test per STP-9.0, RCS Leakage Test, due to a suspected

leak.

The following events occur:

Time 0800 - The OATC verifies reactor power, RCS temperature, pressurizer

Time 0840 - The OATC verifies the reactor makeup control system is in automatic.

- Chemistry depadment is notified of the performance of STP-9.0.

Time 0845: - The Shift Chemist secures from taking a primary sample.

Time 0900 - Operators commence taking data for STP-9.0.

Time 0938 - Shift Chemist performs a BF on the in sewice CVCS demineralizer.

Time 0940 - The OATC completes a 15 gal boration through the boric acid blender.

Time 8945 - The operators secure from taking STP-9.0 data.

pressure and Bevel stable.

- The OATC verifies VCT level is at 40%.

After completion of the test, the shift supervisor states that the surveillance is

inaccurate.

Which ONE of the following caused STP-9.0 to be inaccurate?

A. A primary sample was taken 45 minutes prior to the start of the surveillance.

B. Shift Chemist performance of the DF on the in service CVCS demineralizer.

C. A boration was pe~ormed during the surveillance.

D. Data was only taken for 45 minutes.

A - Incorrect; Primary samples taken prior to the performance of the STP will not affect

the test. It must be verified that Reactor power and Reactor coolant temperature are

constant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to the test.

- Correct; No sampling of the RCS or CVCS shall be performed.

C - Incorrect; A boration of less than 10 gals will invalidate this test due to inaccuracies.

This boration was in excess of 10 gals and flow was through the boric acid blender

only five minutes before data taking was securred. Five minutes is of short enough

duration that the subsequent poweritemperature change will not invalidate the data.

D - Incorrect; It is preferred that data is taken for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> but in any case at least 30

887 in kl tes.

2.

Given the following trends on the 1A RCP:

Parameter

TIME

0200

0230

0300

0330

Motor winding temp (OF)

Pump shaft vibration (mils):

12

Pump frame vibration (mils):

3

1. I

seal DP (psid):

1. I

seal outlet temp ("F)

31 2

21 2

201

Lower seal water BRG temp (OF)

195

Motor lower radial RG ternp(of) 167

Motor upper radial BRG temp("F) 167

31 5

13

4

223

220

200

188

188

320

14

5

223

236

205

195

195

324

15

5

235

240

21 8

198

198

What is the earliest time that the operators are required to trig 1A RCP?

A. 0200

B. 0230

C. 0300

D. 0330

Source: Modified from Farley Bank Questions #RCP-40301 DO8 007 and

1. RCP-40301 D4 1 816

A - Incorrect; Temps do not exceed setpoints ( 225°F for #1 seal outlet temp) and Vibs

are still low enough to remain operating.

B - Inorrect; Vibs are still low enough to remain operating.

C - Correct; Vibs per above will CAI for .a reactor trip and turn off the pump.

Annunciator HH4

7.1 IF FRAME VlB

INCREASE EXCEEDS 0.2 MIL PER HOUR, THEN PERFORM THE

FOLLOWING:

TION HAS REACHED 5 MILS AND THE RATE OF

7.1 .I

TRIP THE REACTOR

7.1.2 STOP THE AFFECTED RCP

D - Incorrect; This is not the earliest time but is the time to trip due to shaft vibration.

3.

The reactor is at 85% power with all systems operating normally. Control bank D is at

225 steps. Control rod H6 rod bottom light energizes, and annunciator FE3, ROD AT

BOTTOM, alarms; the reactor does not trip. Reactor power is currently at 78%.

Which ONE of the following describes the required actions that should be taken in

response to this event?

A. Reduce turbine load as necessary to match Tavg with Tref.

B. Attempt to match Tavg with Tref using manual rod control.

C. Enter AOP-49, Malfunction of Rod Control System, and trip the reactor.

B. Increase boron concentration to match Tavg with Tref.

Source: Modified from Farley Exam Bank Question #AOP-l9.0-52520S02 002

Ref: AOP-19.0

A - Correct; IAW AOP-19.0 Steps 1-5

B - Incorrect; Manual rod control is not recognized as an option for returning Tavg to

Tref.

C - Incorrect; This is the answer before the change to AOP-19. This is still the answer

for multiple dropped rods.

B - Incorrect; Increasing boron concentration would increase the deviation between

Bavg and Tref. The RCS should be diluted.

4.

Unit 1 is operating at power, '1A BAT is "on-service" and 'IB' BAT is on "RECIRC".

VCT level has lowered over time as expected due to RCS inventory losses and has

reached the auto makeup setpoint. An auto makeup to the VCT has started.

Which ONE of the following correctly lists the pump($) which will be started in response

to the auto makeup signal?

A. 1B reactor makeup water pump and 1A boric acid pump will start

B. 1 B reactor makeup water pump only, 1 B boric acid pump is already running

C. 1A reactor makeup pump and 1A boric acid pump will start

L3. l A reactor makeup water pump only, 1B boric acid pump is already sunning

Source: Farley Question Bank Question #RXM/U-40301G07

A - Correct; Per OPS-52101 G the 1 B makeup water pump starts on auto makeup

signal and the 1A 'on-service' BAT pump will start.

B - Incorrect; 1A BAT pump start circuitry is independent of the other BAT pump run

circuitry.

C - Incorrect, The 1A makeup water pump does not start on auto makeup to the VCT, it

starts on the manual. dilute and alt dilute.

D - Incorrect; The ?A makeup water pump does not start on auto makeup to the VCT, it

starts on the manual, diiute and alt dilute. ZA BAT pump start circuitry is independent of

the other BAT pump run circuitry.

--

5.

Which ONE of the following explains the bases fur controlling the volume control tank

(VCT) pressure with hydrogen when the plant is at power?

A. To provide adequate suction pressure during multiple charging pump starts.

B. To provide adequate charging pump recirculation backpressure during normal

operations.

C. To ensure proper coulant flow across RCP seal #2.

D. Ensures hydrogen concentration in the RCS is controlled for oxygen scavenging.

Source: Farley Exam Bank Question #CVCS-48381 F02 821

A - Incorrect; The minimum volume in the VCT provides adequate suction pressure for

the charging pumps the pressure requirement is for seal flow and Oxygen cuntrol.

B - Incorrect; The charging pump miniflow recirculation lines which return to the VCT

contain orifices to provide back pressure.

C ~ Incorrect; This is the reason that the VCT is controlled at a minirnum of 18 psig but

not the reason for using Hydrogen.

D - Correct; During plant startup from a cold shutdown condition, hydrazine is added as

an oxygen scavenging agent. Hydrazine is not used at any time other than startup

from the cold shutdown condition. The hydrazine solution enters the RCS in the

same manner as LiOH. In order to control and scavenge oxygen produced by

radiulysis of water in the core region, hydrogen from the waste processing system is

added to the VCT to maintain a hydrogen concentration of 25 to 50 cclkg of reactor

coolant. A pressure regulating valve maintains a minimum pressure of 18 to 20 psig

in the vapor space of the VCT and can be adjusted to provide the correct hydrogen

concentration.

6.

Given the following:

.

.

- Unit 1 is operating at 100% power.

- Unit 2 has experienced a loss of site power (LOSP) while in mode 5.

Which ONE of the following describes the power that the 2A and 28 RHR pumps will

be supplied from?

(Assume all systems and components operate properly.)

A. RHR pump 2A: 1-2A Diesel Generator through the 2F 4160 Volt bus.

RHR pump 2B: 2B Diesel Generator through the 2G 4160 Vdh bus.

B. RHR pump 2A: 1-24 Diesel Generator through the 2 6 4160 Volt bus.

RHR pump 2B: 25 Diesel Generator through the 2F 4160 Volt bus.

6. RHR pump 2A: 28 Diesel Generator through the 2 6 4160 Volt bus.

RHR pump 2B: 1-2 A Diesel Generator through the 2F 4160 Volt bus.

D. RHR pump 21%: 28 Diesel Generator through the 2F 41 60 Volt bus.

RHR pump 25: I-2A Diesel Generator through the 2 6 4160 Volt bus

Source: Modified from Farley Test Bank Question #RHR-40301 KO6

OPS 40301K

~ A pump is the A train pump

.

..

Alternate $Emergency

1

Bus

Normal 7

160V Bus F

SG?iiZpjK-~- S/U Xfmr 1 (2)B

l/%A Diesel Gen

I

160v Bus.'G

S N Xfmr I

(2)B

SIU Xfmr 1 (2)A-

1 (2)B Diesel Gen

A. Correct - The 1-2A DG will start and align to the 2F 4160V bus and 2B DG will star!

and align to the 2G 4160V bus.

B, Incorrect - The 1-2A DG will star! but does not align to the 26 4160V bus and 25 DG

will start but does not align to the 2F 4160V bus. (Correct DG, Wrong bus)

C. Incorrect - The 1-24 DG will start but does not align to the 2 6 4160V bus and RHR

pump 2A is not powered from the 2G 416OVbus; and 28 BG will start but does not align

to the 2G 4160V bus and RHR pump 2B is not powered from the 2F 4160V bus.

(Wrong DG, Wrong bus)

D. Incorrect - The 1-2A DG will start but does not align to the 2G 4160V bus aliough,

RHW pump 2B is powered from the 2 6 4I6OVbus; and 25 DG will start but does not

align to the 2F 4160V bus although, RHR pump %A is powered from the 2F 4160V bus.

(Wrong De, Correct bus)

--f

.

.

~

_.

7.

Unit 1 has just completed a shutdown to Mode 5 with both trains of WHR in service.

The operators are in the process of placing the 'B' train RHR in standby.

- 'A

train RHR flow has been increased from 1500 gpm to 2300 gpm on the

- 'B' train RHR flow has been decreased from 1500 gprn to 900 gpm on the

- The WHW miniflow valve controls are in the 'AUTO' position.

discharge of 'A train RHR pump.

discharge of 'B' train RWR pump.

Which ONE of the following describes the position of the RHR miniflow control valves?

FCV-602A

FCV-602B

A.

CLOSED

CLOSED

E).

OPEN

CLOSED

C.

CLOSED

OPEN

D.

OPEN

OPEN

A ~ Correct; For Unit 1 the RHW miniflow valves do not go OPEN until RHR pump

discharge flow decreases below 950 gpm and are CLOSED when RHR pump

discharge flow is above 1399 gpm. With both pumps initially being above 1399 gprn

and not yet less than 750 gprn, both FCV-6028 & B will be CLOSED.

B - Incorrect; For Unit 1 the RHR miniflow valves do not go OPEN until RHR pump

discharge flow decreases below 750 gpm.

C ~ Incorrect; Correct for Unit 2, the RHR miniflow valves go OPEN when RHR pump

discharge flow decreases below 1334 gpm and are CLOSED when RHR pump

discharge flow is above 2199 gprn.

D- Incorrect; Correct if thought that valves were controlled off of total RHR flow.

1 B accumulator discharge isolation valve. The disconnect

cannot be closed.

Which ONE Q

lowing actions should the operator take with

accumulators and

more cold water to

B. When accumulator isol

isolate 1A and I C

"hard" bubble in the pressurize

the loops that could accumulate at

"hard" bubble in the pressurizer.

high points, potentially resulting in a

D. Immediately vent the 1 B a

Reactor Coolant Pumps

he possibility of gas binding of

1. ESP-1.2-52531 FO3

A Incorrect; Cor

iven is why not to inject

accumulators d

PTS condition.

PS-5253OC Page 23

rrect; Incorrect reason for venting the accumulator.

9.

Given the following:

- ECP-0.0, "Loss of All A 6 Power", has the operator verify the RCS is isolated by

verifying HV-8149A, HV-8149B5 and HV-8149'2, letdown isolation valves, are

closed.

- The RNO is to check HV-8275A and HV-81758, letdown line penetration room

isolation valves.

Which ONE of the following is the reason HV-8149A, B, and C are checked

preferentially to HV-8175A and HV-81 SfiB?

A. Keeps the loss of coolant accident inside containment.

B. Prevents flashing in the regenerative heat exchanger.

6. Prevents RCS flow to the PRT via the letdown relief line.

B. To prevent inadvertant closure of LCV-459 and 460.

Source: Farley Exam Bank Question #E6-0.01.1.2-52532AQ8 008

Reference: ECP-0.0

A ~ incorrect; a loss of coolant due to a loss of all AC power would be from the RCP

seafs and letdown isolation does not impact the seal failure.

B - Incorrect; both the 8149 or 8175 valves would stop flashing in the heat exchanger.

C - Correct; the reason for isolating letdown is to conserve inventory in the RCS.

D

~ Incorrect; closing either set of valves would not close LCV-459 and 460.

10.

A leak has developed in the 'a' RCP thermal barrier heat exchanger. CCW train 'A is

the in service train.

Which QNE of the following describes the correct sequence of events that would occur

with no operator involvement?

A. AA4 (AB4), CCW SRG TK LVL A (B) TRN HI-LO, annunciator lit;

DD2, RCP THRM BARR CCW FLQW HI, annunciator lit;

CCW from RCP THRM BARK HX HI FLOW Isolation Valves, HV-3045 and

HV-3184 90 closed

B. AA4 (AB41, CCW SWG TK LVL A (B) TRN HI-LO, annunciator lit;

HV-3184, RCP THRM BARR HX HI FLQW Isolation Valve, goes closed;

BD2, RCP THRM BARR CCW FLOW HE, annunciator lit;

HV-3045, RCP THRM BARR HX HI FLOW Isolation Valve, goes closed

6. AA4 (A34), CCW SRG TK hVL A (B) TRN HI-LO annunciator lit;

DD2, WCP THRM BARR CCW FLOW HI, annunciator lit;

HV-3045, RCP THRM BARR HX HI FLOW Isolation Valve, goes closed;

HV-3184, RCP THRM BARR HX HI FLOW Isolation Valve, goes closed;

BB3. CCW FLOW FROM WCP OIL CLRS LO,

annunciator lit

D. HV-3184, RCP THRM BARR HX HI FLOW Isolation Valve, goes closed;

AA4 (AB4), CCW SRG TK LVL A (9) TRN HI-LO, annunciator lit

A - Correct; The CCW leak from the higher pressure RCS source into the CCW system

causes CCW tank level to increase (AA4); high flow in the CCW line from the RCS fluid

causes BB2 to alarm and HV-3045 to shut stopping flow; Pressure increases in CCW

pipping and shuts HV-3185 in order to prevent overpressurization of the CCW system.

Pressure and flow are sensed on the thermal barrier CCW discharge line. The

pressure sensors (PI-31848, B, and C) signal HV-3184 to shut when pressure

increases to 75 psig. Flow element FE-3045 shuts HV-3045 if the flow increases to

160 gpm.

3 - Incorrect; Once HV-3184 is closed flow will no longer be going past FE-3045

therefore, BD2 wlll not alarm if if had not done prior to the closing of HV-3184 and

HV-3045 will not get a close signal.

C - Incorrect; The closing of the HV-3045 and HV-3184 does not affect the flow path

through the RCP oil cooler.

D - Incorrect; Once HV-3184 goes closed no more fluid is added to the CCW surge

tank therefore, if this alarm did not alarm prior to the closing of HV-3184 if will not alarm

afterward (unless check valves in the CCW to thermal barrier leak and this would not

be a reasonabie argument). The thermal barrier check valves shall isolate the CCWS

piping upstream of the RCPs from the RCS in the event of a rupture of the reactor

coolant pump thermal barrier. On a thermal barrier failure, the check valves shall

prevent a pressure transient from propagating to the low pressure piping.

11.

Given the following plant conditions:

- Unit 1 RCS has a stuck open pressurizer safety valve.

- Appropriate Operator response actions have been taken.

- Pressurizer pressure is stable at f350 psig.

- Containment temperature is I

55~.

- Actual pressurizer level is 50%.

Select the combination below that fills in the following blanks concerning the effects of

these conditions on the pressurizer level indicated on level channel 1 (459) indicator.

The affect of pressurizer pressure at 1350 psig will cause the indicated pressurizer

level to read JjQ-

actual level; the affect of containment temperature at 255% tends to

make the indicated pressurizer level read

than actual level.

A. (X) Below; (Y) Higher

B. (X) Below; (Y) Lower

C. (X) Above; (Y) Higher

D. (X) Above; (Y) bower

REF: Farley Exam Bank #1286, E-O/ESP-0.0-52530A06 O? 4

12.

Unit 2 is in MODE 3 at 547'F and 2235 psig when a fault condition results in the loss of

the 2A 4160V bus. In order to stabilize RCS pressure, the 80 manually energizes the

avaiiable backup heaters and attempts to control RCS pressure by manually operating

the pressurizer spray valves.

Which ONE of the following statements best describes the required control board

actions necessary to stabilize pressure?

A. Loop A spray valve, PK-444C, should be manually closed and loop B spray valve,

PK-4445 must be used to control pressure.

B. Loop B spray valve, P%(-444C, should be manually closed and loop C spray valve,

PK-444D, must be Lased to control pressure.

C. Loop C spray valve, PK-444C, should be manually closed and loop B spray valve,

PK-444B, must be used to control pressure.

8. Loop B spray valve, PK-444D, should be manually closed and loop A spray valve,

PK-444C, must be used to control pressure.

Source: Farley Test Bank Question #PZR PRS/LVL-522011-111 009

Ref: AOP-4.0

A. Correct

B. Incorrect, Wrong loops referenced for both PK-444C and 444D.

C. Incorrect, Wrong loop referenced for PK-444C.

5. Incorrect, PK-444D used to control pressure. PK-444C is isolated due to loss of 2A

RCP.

13.

Which ONE of the following describes why the pressurizer spray valves have a

continuous flow design feature?

Provides adequate flow to:

A. maintain variable heater output at a minimum value to prevent heater burnout.

EL maintain the surge line warm to prevent severe thermal shock associated with a

pressurizer insurge.

C. prevent PRZR/RCS differential temperature limits from being exceeded.

D. prevent spray nozzle from experiencing severe thermal shock upon initiation of

spray flow.

Source: Modified from Farley Exam Bank Question WPZR P!?S/LVL-52201 H02 003

A - Incorrect; the continuous spray flow of 0.5 gpm per spray valve does not provide

adequate flow, procedures have been modified to ensure adequate spray flow is

provided for this by the energizing of Pnr heaters.

B

~ Incorrect; the continuous spray flow of 0.5 gpm per spray valve does not provide

adequate flow.

C -Incorrect; the continuous spray flow of 0.5 gpm per spray valve does not provide

adequate flow.

D - Correct; the continuous spray flow of 0.5 gpm per spray valve will provide adequate

flow to keep the spray valves warm.

14.

Unit 1 has experienced a reactor trip. The crew had transitioned to ESP-0.1 Reactor

Trip Response, when a large break LQCA occurred.

-

SI actuation did not occur and the operators are unable to start any HHSl

pumps.

~

RCPs are running.

-

A loss of containment integrity caused containment pressure to peak at 10 psig.

- The crew is verifying each train of CCW started per step 6 of EEP-0.0, Reactor

trip or Safety Injection when the SPA reports that RCS subcooling has

decreased to O'F.

Which ONE of the following describes the correct operator response to this situation?

A. Trip all running RCPs and remain in EEP-0.

B. Do not trip the running RCPs and remain in EEQ-0.

C. Transition to FWP-C.1, "Response to Inadequate Core Cooling".

B. Transition to FRP-6.2, "Response to Degraded Core Cooling".

Source: Farley Exam Bank Question #E-O/~SP0.0-52530AO~

002

Ref: EEP-0

A - Incorrect; EEQ-0 fold out page RCP trip criteria has not been met due to failure of

the HHSl pumps

B - Correct; RCPs are not tripped by fold out page criteria. Transition criteria to other

procedures have not been met.

C - Incorrect; Transition to FRP-C.1 is made if CETC's are 9 120Q OF, this can not be

the case if subcooling has just decreased to 0 OF with a LOCA in progress.

D - Incorrect; Transition to FRP-C.2 is made if CETC's are 9 700 OF, this can not be the

case if subcooling has just decreased to 0 OF with a LOCA in progress.

a 5.

Given the following conditions on Unit 1:

-

Reactor Power at 100%.

-

-

Pressurizer level control system in automatic.

The median Pavg signal to the level control system fails to 50Q'F.

Which ONE of the following describes the effect on the pressurizer level control

system?

A. Charging will reduce to a minimurn, HA2, "PRZR LVL DEV HI B/U HTRS ON"

annunciator will actuate, pressurizer level will fall to 21 4% and stabilize.

B. Charging will reduce to minimum, HB2, "PRZW LVL DEV Lo" annunciator will

actuate, pressurizer level will fall to 21.4% and stabilize.

6. Charging will increase to 120 gpm, "HA2: "PRZR LVL DEV HI B/U HTRS ON"

annunciator will actuate, pressurizer level will rise, eventually the reactor will trip on

high pressurizer level at 92%.

D. Charging will increase to 120 gpm, HB2, "PRZW LVL DEV LO" annunciator will

actuate, pressurizer level will rise to 54.9% and stabilize.

Source: Farley Exam Bank Question #PZR PRSILVL-52201 HI2 005

A - Correct; Charging will reduce to a minimum and the alarm will come in. It actuates

at +5% above normal program value and normal value is now 2f .4%.

5 - Incorrect; Charging will reduce to 547 value of 22.4 % and the Pnr dev lo annun. will

not actuate at -5% below program value b/c level will be above program level.

6 & D - Incorrect; Charging will not increase because actual level is now seen as

greater than program level, charging flow will decrease.

16.

Which ONE of the following contains ONLY protective trips that are intended to protect

the reactor from a DNB concern?

A. OTDT, Low pressurizer pressure, and OPBT.

B. bo-Lo SGWL, Low pressurizer pressure, and O f DT.

C. OTDT, Low pressurizer pressure, and Reactor coolant low flow trips.

B. Reactor coolant low flow trips, bo-bo SGWL, and High pressurizer Level.

Source: Farley 2000 NRC Exam

A Incorrect; OPBT (overpower concern) is not a DNB concern.

B ~ Incorrect; Lo-Lo SGWL (preserves heat sink) and QPDT are not DNB concerns.

C - Correct

D Incorrect; ~Q-Lo

SGWL and high pressurizer level (Hi Pressurizer pressure concern)

are are not BNB concerns.

17.

A large-break LOCA occurs combined with a malfunction of the ESF sequencers which

results in delaying the energizing of ESF components. Which ONE of the following is

correct concerning the effects on the fuel during this situation?

A. Cladding failure can occur as the core experiences an uncontroiled cooling due to

vaporization of reactor coolant.

B. Structural integrity can be lost as delayed cooling can lead to fuel temperatures in

excess of ECCS acceptance criteria, resulting in excessive clad oxidation and

weakening.

C. Minimal effects will be seen as reflux cooling is sufficient to cool the core for up to

ten minutes after the onset of a large break LOCA.

B. A natural circulation cooldown of the fuel can be adversely impacted due to

excessive reactor coolant blowdown.

Source: Farley Exam Bank Question #BG SEQ-40102DQ2 01 1

B - Correct; Failure to provide ESF flow to the core will result in increasing fuel

temperatures resulting in structural integrity loss.

18.

Unit 1 is operating at 45% power when the foilowing annunciators come into alarm:

-

Annunciator DC2, WCP #1 SEAL LKQF FLUW HI.

~

Annunciator DC3, RCP #I

SEAL LO DP.

The WO referred to the appropriate ARPs, then determined that #I

seal leakoff flow

was off-scale high and the #1 seal DP was indicating off-scale low.

Which ON of the following describes the correct sequence of actions required for the

above situation?

A. Close the #I

seal return valve, ramp down power to less than 30% and remove the

affected RCP from service within 30 minutes.

B. Close the #I

seal return valve, trip the reactor, then stop affected RCP.

6. Ramp down power to less than 30%, stop affected RCP, then close the #I

seal

return valve after RCP coastdown.

B. Trip the reactor, stop affected RCP, then close the #I seal return valve after RCP

coastdown.

Source: Farley Test Bank Question #-O/SP-8.8-52530A02 022

A - Incorrect; Actions of ARP DC3 if #I

Seal Leakoff valve is not open.

3 - Incorrect; Incorrect order of actions, the #I

Seal beakoff valve should not be shut

until after the reactor is tripped and the RCP securred.

C - Incorrect; These actions will get the affected RCF off line but a reactor trip is

required per the applicable ARP.

B - Correct; These are the actions required by ARP DC2 (Step 4 RNO) for Seal Leakoff

greater than 8 gpm.

19.

Given the following Unit 1 initial plant conditions:

Steam generator level on program.

-

-

Turbine load at 50%.

Which ONE of the following plant conditions demonstrates the EARLIEST time when

AMSAC will actuate?

2/3 Steam Generator

Steady State Turbine Load

NW Level

PT-2446

PP-2447

A. Time8400

15%

45%

46%

3. Time0705

12%

42%

43%

C. Time 0710

9%

40%

41 %

D. Time07q5

5%

38%

39%

Source: Modified from Farley Exam Bank Question #SG PROP-52201K07 008

A - Incorrect; AMSAC will not be actuated because S/G levels are too high with turbine

power above 40%.

E3 - Incorrect; AMSAC will not be actuate bemuse SG levels are too high with turbine

power above 40%.

C - Correct; AMSAC will actuated because SG levels are below 10% with turbine power

above 40%.

B - Incorrect; AMSAC will not actuate even with SG levels below 40% since turbine

power is below 40%.

20.

Given the following:

• Unit I is operating at 100% power.

• All controls are in the normal full power lineup.

4 Pressurizer level is falling.

• VCT level is rising.

4 RCP SEAL %NJ FLOW LO alarm is lit.

REGEN HX LTDN FLOW DISCH TEMP HI alarm is lit.

CHG HDR FLOW H I 1 0 alarm is lit.

Which ONE of the following describes the event that has occurred?

A. boss of charging.

B. Letdown isolation.

C. Small break LOCA.

8. Pressurizer PORV failed open.

Source: Farley Exam Bank Question #CVCS-40301 FO7 032

REFERENCE

I.

I-ARP EA2, DD1, BE1

A - Correct; all conditions given would be a result of loss of all charging flow.

B - Incorrect; During a loss of letdown, PRZR level would be rising and VCT level would

be lowering.

C & D - Incorrect; ff a SBLOCA or PORV OPEN had occurred, PRZR level could be

falling (depending on break size) but VCB level would also be falling due to increased

charging flow and constant LTBN flow. REGEN HX LTDN FLOW DISCH TEMP HI

alarm would also not be in because there is rnax. cooling occuring due to the high CHG

flow. CHG WDR FLOW HI-LO alarm and RCP SEAL INJ FLOW LO alarm could both

be in alarm.

2t. Plant conditions are as follows:

- Unit 1 was at 100% reactor power.

- Unit 2 was in Mode 5.

- A dual-unit Loss of Offsite Power has occurred.

- All EDGs have started and tied onto the vital buses.

- Vital load sequencing has been completed.

- FNP-1-EEQ-0, "REACTOR TRIP OR SAFETY INJECTiON" has been entered

- While the immediate actions are being completed, a Safety Injection (SI) signal

on Unit I.

is received on Unit 1.

Which ONE of the following describes the response of the Unit 1 Containment Fan

Coolers from the time the SI signal is received?

A. All fan coolers load shed on the SI signal and sequence back onto the vital buses in

slow speed.

3. All fan coolers load shed on the SI signal, and selected fan coolers sequence back

onto the vital buses in slow speed.

C. Selected fan coolers do NOT load shed OR the SI signal, and the non-selected fan

coolers remain &-energized.

83. Selected fan coolers do NOT load shed on the SI signal, and the non-selected fan

coolers sequence back onto the vitai buses in slow speed.

Source: Farley NRC Exam 2001

Original Source: Farley NWC Exam 1999

A - Incorrect, The selected fan coolers do not load shed for the given conditions.

3 - Incorrect, The seiected fan coolers do not load shed for the given conditions.

C- Correct

D - Incorrect, The nonselected fans do not start on an SI with LOW.

_-

22.

Unit I

is in Mode 4 with A'

Train WHR in service and the following conditions:

- 1 B RHR Pump is out of service for maintenance

The "B" Train of SFP cooling is in service

CCW SRG TK LVL A@) TRN HULO annunciators AA4(AB4) are received and

it is confirmed that surge tank level is increasing.

RE-Ol78, 'A' Brain CCW radiation monitor, indicates increasing radiation levels

in the CCW system.

Which ONE of the following most correctly describes the cause and operator response

for the plant conditions above?

A. The 1A RHR pump seal cooler has developed i) leak. CCW can be isolated to the

seal cooler so long as RHR temperature does not exceed 150°F.

B. The ?A WHR heat exchanger has developed a tube leak. 'A' Train RHR must be

shut down and AOP-12, 'I Residual Heat Removal System Malfunction," should be

entered.

C. The 1A RHW heat exchanger has developed a tube leak. '4' Train CCW must be

shut down; however, operation of 'A' Train RHR may continue.

D. The l A CCW heat exchanger has developed a tube leak. Operation of 'A' Train

CCW may continue.

Source: Farley Exam Bank Question #AOP-12.0-5252OL02

A ~ Incorrect; Seais are cooled by RCS fluid circulated through an external heat

exchanger cooled by CCW.

B - Correct; An RHR heat exchanger leak will result in inleakage to the CCW system

that will show up as increased surge tank level and increased radiation levels.

C - Incorrect; AOP-22 should be entered to establish an aiternate means of DHR.

5 - Incorrect; AOP-12 should be entered to establish an alternate means of DHR.

23.

Given the following conditions:

T&Ja

&?PNS&EJ\\ B c e E m a d AR%N-

- Unit "I has experienced a significant LOCA.

- Si has actuated and has not been reset;

- All components and systems have operated as designed.

- Per EEP-1, Loss of Reactor or Secondary Coolant, CCW flow has been

The plant has tripped;

established to both trains of RHR when Annunciator AA4(AB4), CCW SRG TK

LVL A(B) TRN HI-LO, alarm came in, followed shortly by Annuciator 865, CCW

SRG TK LVL B TRN LO-LO, alarm

~

The OATC reported the following:

- the 1A CCW Pump has tripped on overload,

- the 1B CCW Pump is in AUTO not running and is aligned to 'K Train,

- the 1C CCW Pump is running,

- the 'B' train surge tank Ievd is continuing to decrease.

Which ONE of the following best describes this situation?

A. The 1B CCW pump should not have started. Attempts to refill the surge tank

should be made and the I C Chg and 1B RHR pumps should be immediately

secured.

B. The 1B CCW pump should have started. AOP-9.0, Loss of Component Cooling

Water. should be entered.

C. The 1 E3 CCW pump should ,r& have started. AOP-9.0, Loss of Component Cooling

Water, should be entered.

D. The I

B CCW pump should have started. However, the 1 B CCW pump should

-

be started, and all A train CCW loads should be secured.

Ref: AOP-9.0

A ~ Correct; With the swing pump (1 B CCW) aligned to the A train ( I C CCW pump) the

tripping of the 1A CCW pump on overcurrent would not cause the swing pump to start

even with an SI signal. Attempts should be made to fill the surge tank and the swing

pump started.

B

~ Incorrect; The swing pump will not automatically start unless aligned to that train.

B - Incorrect; The swing pump will not automatically start unless aligned to that train.

24.

What prevents clogging of the containment spray nozzles following a design loss of

coolant accident while on recirculation?

A. Anti-vortex blades create a centrifugal force to keep large particles and debris from

entering the sump suctions.

3.

Duplex filters on the discharge of the pumps remove particles large enough to clog

the spray nozzles.

C. The screens in the recirculation sump will block any particles big enough lo clog the

nozzles.

D. Accident analysis assumes that there will be no particles or debris loose in

containment that will be larger than the spray nozzle openings.

Source: Farley Exam Bank Question #CS&CQQL-40302D02 006

The spray nozzles, which are of the hollow cone design, are not subject to clogging by

particles less than 114 inch in sine and produce a small drop size that will maximize the

total cooling and iodine removal surface area when operating at the design pressure

differential of 40 psi. The stainless steel spray nozzles have a 3/8 inch diameter orifice,

which is iarger than the 0.120 inch (1/8 inch) screen grating covering the containment

sumps. Therefore, all particles large enough to clog the nozzles will be screened out

before entering the recirculation piping.

A - Incorrect; anti-vortex blades are present in the sump suction to improve flow

conditions to the pumps, thus minimizing the potential for cavitation,

B - Incorrect; there are no filters on the discharge of the pumps.

6 - Correct; screens on the recirc sumps have openings sized such that particles and

debris large enough to clog the spray nozzles can not get past the screens.

D - Incorrect; accident analysis assumes that particles and debris will be blocked from

entering the spray pump suctions by the sump screens.

25.

Unit 2 is at 100% power when the following occurs:

~ Annunciator HCZ, PRZR PRESS HI-LO, comes into alarm.

It has been determined that a failure of the controlling pressurizer pressure channel

has occurred and actual pressure is 2325 psig. The Pressurizer Pressure Master

Controller M/A station PK-444A has been taken to MANUAL.

Which ONE of the following describes the action required to return actual pressure to

its normal value?

A. Increase the M/A station output (% demand).

B. Decrease the M/A station output (% demand).

C. Raise the pressure setpoint adjustment.

D. bower the pressure setpoint adjustment.

Source: Farley Exam Bank Question #PZR PRS/LVL-52201 H08 052

A - Incorrect; This will cause pressure to increase further by the energizing of heaters.

El

~ Correct; This will cause the spray valve(s) to open resulting in a decrease in

pressure returning pressure to the normal value of 2235 psig.

C - Incorrect; This is the wrong direction to adjust the setpoint and with the controller in

manuat this will be ineffective.

D - Incorrect; With the controller in manual this will be ineffective.

26.

Plant conditions are as follows:

Unit 1 has just completed a refueling outage and is in Mode 5.

2 of the 3 baskets.

During the outage the trisodium phosphate (TSP) crystals were removed from

• Due to an oversight the 2 baskets were not refilled with TSP.

Which ONE of the following states the consequences these conditions would have if a

design-basis LOCA were to occur after the plant is started up and operated at full

power for several days?

A. The ability of the emergency core cooling system to maintain the core cool would

be affected and could result in significant core damage.

8. Iodine levels in the containment atmosphere for the long term would NOT be

affected since it would be removed by the containment spray system.

C. The ability of the sump water to maintain iodine in solution would be limited due tu

the reduced amount of TSP available in the containment sump.

D. There would be no effect since 1 TSP basket containing the minimum volume of

crystals is adequate to perform ECCS recirculation fluid pH control.

Source: Farley exam bank Question #CS&COOL-40302DI 1

A. incorrect - TSP provides pH range for keeping radioiodine in solution and mitigating

the impact to stainless steel components due to the low pH of the RWST solution; has

no impact on the ability to cool the core

B. Incorrect - Containment spray removes radioiodine and TSP required to maintain

radioiodine in solution in the ECCS sump

C. Correct ~A reduce volume of TSP would result in a reduced ability to maintain

radioiodine in solution in the ECCS sump

D. Incorrect - Technical specifications requires 3 TSP baskets; each at minimum

volume to mitigate the consequences related to fuel damage and fission product

release, in particular

~ radioiodine, as a result of a design basis LOCA.

-

27.

Given the following plant conditions:

~

A large break LOCA has occurred on Unit 2 thirty minutes ago.

-

Hydrogen concentration inside containment is 4.5%.

Which ONE of the following actions should be taken to reduce hydrogen

Concentration?

A. Place only one electric hydrogen recombiner in service within the next 30 minutes

by first verifying the PWR A5J potentiometer is set to zero (0) prior to turning on the

PWR OUT switch and then set at a power setting of 100 kilowatts.

B. Place the post accident containment venting system in service within the next 30

minutes and reset the vent flow integrator (FQI-3533) to zero prior to commencing

the venting flow by depressing the reset push button located on the BOP.

C. Place the post accident containment venting system in service within the next 30

minutes and reset the vent flow integrator (FQll-3533) to zero prior to commencing

the venting Row by de-energizing the flow intergator using the ON-OFF switch on

the Hydrogen Recombiner Controi Panel.

5. Place both electric hydrogen recombiners in service within the next 30 minutes

by first verifying the PWR ABJ potentiometer is set to zero (0) prior to turning on the

PWW OUT switches and then set each at a power setting of 58 kilowatts.

Source: Modified from Farley Bank Questions #POST LOCA40302E09 8 #POST

LOCA40302E11

A ~ Incorrect; Hydrogen recombiners are not used when hydrogen concentration is

above 4%.

B - Correct; The post accident venting system is placed into service within one hour of

the LOCA and is operated from the BOP

C - Incorrect; This is not how the flow integrator is set to zero.

B - Incorrect; Hydrogen recombiners are not used when hydrogen concentration is

above 4%.

-

28.

Due to an anticipated transient without a trip, FRP-§.I, "RESPONSE TO NUCLEAR

POWER GENERATION/A?WT", is entered.

The following conditions exist:

- Reactor trip breakers A & E indicating lights are RED.

- All four (4) turbine throttle valves are closed, and all available AFW pumps are

running.

While performing step 6 of FWP-S.7, the Reactor trip breakers are opened locally.

Which ONE of the following should the team perform?

A. Perform the first 95 steps of EEQ-Q while continuing with FRP-S.1.

B. Transition to E.$-0, perform the first 15 steps of EEP-0, then return to FWP-S.1.

C. Immediately return to procedure and step in effect, Le., EEP-0.

B. Continue with procedure and step in effect, Le., FRP-S.4

~

Source: Modified from Farley Bank Questions #FRP-S-52533A08 009 &

1. FRP-§-52533A08 004

REFERENCE: FRP-§.I

A - Incorrect; FRP-S.1 is entered, you can not leave the procedure until directed.

B - Incorrect; Returning to EEP-0 is not warranted since FRP-S.1 has not been

comoleted.

C ~ Incorrect; FRP-S.1 would be completed to transition.

D - Correct; Would continue with FRP-S.l untit step 14 is complete regardless of Rx trip

breaker status.

-._

29.

Given the following plant conditions:

A loss of all AC power has occurred on Unit 2.

The actions required by ECP-0.0, LOSS OF ALL AC POWER, are in

progress.

SG atmospheric relief valves are being controlled locally to reduce SG pressure

to less than 200 psig.

A low steam line pressure SI signal has been received.

• Steam line pressure is 350 psig and RCS cold leg temperatures are at 325OF.

You notice both channels of Source Range startup rate go positive then fail low.

The STA monitoring the CSF status trees informs the shift supervisor that there is a

yellow path on subcriticality.

Intermediate range startup rate is reading a sustained +0.2 dpm

Which ONE of the following actions should be taken?

A. Begin an emergency boration.

E. Stop dumping steam and allow the plant heat up to add negative reactivity.

C. Continue to lower SG pressure to c 200 psig

D. Proceed immediately to FRP-S.2.

Source: Farley Exam Bank Question #%C-0.0/.1.2-52532A86 002

Ref: ECP-0.0

JUSTIFICATION:

a. Emergency boration would be an action to mitigate the positive SUR, but cannot be

done without AC power.

b. If SUR is above zero the ECP-0.0 RNO requires securing dumping steam to heat up

the RCS and establish subcriticality. SR must be assumed to have reflected actual

conditions in the core before it was lost since la indications are not consistant with a

subcritical core (IR SUR <-.38PM)

c. If SUR is above zero the ECP-0.0 RNO requires local control of atmospheric relief

valves to raise SG pressure.

d. While in ECP-0.0, CSFs are monitored for information only.

i

30.

EEPS, "Steam Generator Tube Rupture", is in progress, and an RCS cooidown is

desired. The ruptured SG pressure is 920 psig. Desired subcooling is 3537°F. The

RCPs are running, and the plant computer is inoperable. Normal at power CTMT

parameters exist.

What temperature indicator should be used and at what temperature should the RCS

cooldown be stopped?

REFERENCE PROVIDED

A. Core exit TIC monitor indicating 485°F.

B. Core exit T/C monitor indicating 499°F.

6. WR hot leg temperatures indicating 485°F.

D. WW hot leg temperatures indicating 499°F.

Source Farley Bank Question #EEP-3-52530D0? 001

Ref: EEP-3

--

31.

The plant is operating at 200% power with all controls in automatic. Without warning,

PRZW level and RCS pressure begin decreasing. Charging flow automatically

increases, and the PRZR heaters energize. Normal letdown flow isolates, and PRZR

heaters de-energize on low PRZR level. Simultaneously with low PRZR level

indications, high radiation indications from the air ejector radiation monitor and

blowdown line radiation monitors are received in the control room. The reactor trips,

and safety injection occurs on low pressurizer pressure.

Which ON of the following is the explains the cause of the plant response and the

current indications?

A. Main steam line break

B. Main feed line break

c. SGTR

D. RCS cold leg break

Source: Farley Exam Bank Question #EEP-3-52530D02 002

Reference: EEP-3

A - Incorrect; This does not explain the presence of the high radiation.

B Incorrect; this does not explain the presence of the high radiation alarms

C - Correct; These are indications of a SGTR.

D - Incorrect; Does not explain the high radiation at the locations given.

32.

Unit 1 is at 32% power and ramping up. All systems are in automatic and controlling

properly. Control bank "D" is at 72 steps and controlling RCS temperature.

A BEH control system malfunction results in a turbine trip. The control rods drive into

the core 12 steps prior to being taken to MANUAL. The control rods and the steam

dumps are used to restore reactor power to 32%. Bank "D" control rods were raised to

65 steps. The generator trips 30 seconds after the turbine trip. The 4260V buses IA,

ZB and I C transfer to the startup transformers.

Which ONE of the following describes the action(s) should be taken in accordance with

AOP-3.0, Turbine Trip Below P-9 Setpoint?

A. Reduce reactor power to between 8% and Is%, slowly open the atmospheric relief

valves to close the steam dump valves, then swap the steam dumps to the steam

pressure mode of operation.

B. Initiate an emergency boration in order to bring the control rods above the lo40

insertion limit.

C. Reduce reactor power to less than 8%, slowly open the atmospheric relief valves to

close the steam dump valves, then swap the steam dumps to the steam pressure

mode of operation.

D. Maintain reactor power and slowly open the atmospheric relief valves to close the

steam dump valves, then swap the steam dumps to the steam pressure mode of

operation.

Source: FarEey Exam Bank Question #AOP-3.0-52520604 002

A - Incorrect; Power leveb is incorrect, power level is for steam dumps already being in

steam pressure mode.

B ~ incorrect; This is performed if it is desirable to leave the rods in auto

C - Correct; Per step 9 of AOP-3.0 and SOP-18.0, Steam Dump System

D - Incorrect; Power level is incorrect, power level is for steam dumps already being in

steam pressure mode.

33.

Given the foilowing:

In EEP-2, "Faulted Steam Generator Isolation", the operator is cautioned that

any faulted steam generator should remain isolated during subsequent recovery

actions unless needed as a heat sink for RCS cooldown.

Which ONE of the following is the reason for the caution?

A. AFW pumps could reach run-out flow and cavitate, causing damage to the pumps

and possibly rendering them inoperable.

B. Additional steaming from the SG will increase the likelihood of damaging other

equipment, power supplies, or instrumentation in the vicinity of the break.

C. Un-isolating a faulted steam generator could cause an RCS cooldown and risk an

inadvertent return to cfiticality.

D. Reestablishing feed flow to the faulted steam generator would cause SI to reactuate

on high steam flow and interfere with the RCS cooldown to Mode 5.

Source: Farley Exam Bank Question #EEP-2-52530C03 001

Reference: EEQ-2

C - Correct

-

34.

The plant is in UOP-3.1, "POWER OPERATION," at 33% power and ramping up.

All systems are in automatic and controlling properly. Steam dumps are in the Tavg

mode and the control rods are at 7'2 steps on control bank 'D'.

- A malfunction of the DEH control system results in a turbine trip.

- The rod control system is placed in manual and used with the steam dumps to

- Steam dump control is then inadvertantly transferred from the Tavg mode to

stabilize reactor power at 33%.

the steam pressure mode.

Which one ofthe following describes, for the conditions given, assuming NO further

~ p e ~ a t o ~

action, what will be the response of the plant?

A. WCS temperature will decrease and pressurizer level will decrease.

B. RCS temperature will increase and pressurizer level will increase.

C. Steam dumps will modulate to bring steam header pressure to the steam dump

controller setpsint.

D. No effect in steam pressure mode. The steam dumps will continue to control WCS

temperature.

Source: Farley 2002 NRC Exam

Original Source: Farley exam bank: Question # 052520C06003

A - Incorrect, this is the action if the steam dumps were to fly open.

5 - Correct, the steam dumps immediately close when the switch is taken from Tavg

mode to Steam pressure mode.

C

~ Incorrect, steam pressure control output shifts to steam pressure mode in manual

with an output of zero.

D - Incorrect, this is the action if the steam dumps continued to operate in the Tavg

mode.

..

35.

Unit 1 is at 60% power and slowly ramping up.

Which ONE of the following conditions will first result in the loss of condenser steam

dumps?

A. One of the two running Circulating water pumps breaker trips open on overcurrent.

B. One of the Condenser vacuum switches indicates less than 8 inches of mercury.

6.

Both of the Condenser vacuum switches indicate less than 8 inches of mercury.

D. Both of the Condenser vacuum switches indicate less than 10.8 inches of mercury.

Source: Modified from Surry 2002 NRC Exam

A ~ Incorrect; Must have both circ water pump breakers open

B - Correct; Must have both of the Condenser vacuum switches greater than 8 inches

of mercury for Condenser Available C-9. C-9 is disabled with

C - Incorrect; Does not satisfy the C-9 permissive.

D - Incorrect; This is not the vacuum setpoint in inches of mercury, this is the setpoint in

psia.

.-

36.

While holding reactor power at 33% for chemistry, a loss of main feedwater occurred

when the ONeY running SGFP tripped.

Which ONE of the following statements is correct?

A. The WX TRIP ACTUATION switch should be placed in the TRIP position.

E. The main turbine MEW TRIP switch should be placed in TRIP for at least 5

seconds.

C. Reactor power must be rapidly reduced to less than 2%, then manually trip the

main turbine.

D. The main turbine should be tripped manuaDly followed by a manual reactor trip.

Source: Modified from Farley Bank Question #AOP-13.0-5252OM06 002

Ref: AOP-13.6)

A incorrect; A reactor trip is not warranted at power level below 35%.

B - Correct; With power level below 35% this is an immediate action step of AOP-13.

C - Incorrect; This is done after the main turbine is tripped.

D Incorrect; A reactor trip is not warrented at power level below 35% the main turbine

is tripped followed by a power reduction to less than 2%.

-.

37.

Which ONE of the following describes the plant components that are used to provide

remote capability to feed the steam generators with the turbine-driven AFW pump

during a station blackout?

A. 120 vac instrument inverter, 48 vdc battery, air accumulator.

B. AC and DC uninterruptible power supply, 48 vdc battery, air accumulator.

C. AC and DC uninterruptible power supply, auxiliary building 125 vdc battery,

emergency air compressor.

D. 120 vac instrument hverter, auxiliary building 125 vdc battery, emergency air

compressor,

Source: Farley Exam Bank Question #AFW-40201 DO6 003

A - Incorrect; 120 vac instrument inverter does not provide a B/U to the TDAFW pump

B - Correct; Power is supplied from the 48V BC battery to an inverter which then

supplies the HSBP which in turn supplies the TBAFW Speed Control and FCV's

position controller. The inverter also directiy supplies a DC rectifier that supplies power

to open TDAFW Valves, FCV soleniods and TDAFW Control Panel.

C & D - Incorrect; AB 225 v dc battery does not provide a B/U to the TDAFW pump.

-

38.

Considering the ESS Load Sequencer operation during an accident with an LQSP,

which ONE of the following describes the reason($) behind the ESS Load Sequencer

order and time to initiation of power to the various loads?

A. The considerations deal ONLY with maintaining the diesel generator frequency and

voltage within tolerance.

E!.

The considerations deal ONLY with ensuring the starting of the various engineered

safety features are within the required safety analysis response time values.

C. In order to ensure that the diesel generators speed will not decrease below 95% of

nominal value, the largest loads are started first when the diesel generator can best

handle the starting currents.

B. The required response time values of the various emergency safety features are

based on the accident analysis of the plant for the design based accident and the

diesel generator capability.

A - Incorrect; This is onBy one of the reasons.

B

~ Incorrect; This is onBy one of the reasons.

C - Incorrect; Diesel generators speed must be maintained and starting currents must

be allowed to decay between subsequent equipment starts making this a potential

reason.

D - Correct; This is both distractors A and C combined and is the reason for the

sequencer loading. OPS-52103F-40102D

39.

Given the following plant conditions:

-

Unit 2 is at 80% power ramping to 100%.

-

Both SGFPs are operating.

-

All systems are aligned for automatic operation.

-

Annunciator KB4, SGFP SUCT PRESS LO, has just come into alarm.

The Recorder PR-4839 indicates SGFP pressure is 295 psig and slowly

decreasing.

Which ONE of the following is the action required by the operator?

A. Ensure the standby condensate pump starts 10 seconds after pressure has

decreased to 275 psig.

B. Start the standby condensate pump prior to pressure decreasing to 275 psig.

C. Begin a rapid load reduction to 60% in order to remove one SGFP from service.

D. If pressure continues to decrease, manually trip the reactor and enter EEP-0,

Reactor Trip or Safety injection.

Source: Farley Exam Bank Question #AOP-2 3.0-5252QM04 009

Reference: ARP-1 .IO: KB4

A - incorrect; The operator Is instructed by the ARP to start the Cond pump prior to 275

psig.

E3 - Correct; The standby condensate pump will auto start at 275 psig but the ARP

requires it to be manually started prior to reaching 275 psig.

C - Incorrect; A rapid load reduction is required if the standby condensate pump is not

available. There is no requirement to trip one of the SGFPs because there is an

automatic trip on low suction pressure.

D - Incorrect; This action would be appropriate if suction pressure decreases below 275

psig for 30 seconds and the starting of the standby condensate pump has not corrected

the pressure drop.

40.

m.4

WPPedk

Given the following plant conditions:

hdvi dd04

-

Unit 1 is holding at 25% power due to problems with BEH during a plant startup.

-

Rod control is in AUTO, with Bank D rods at 174 steps.

-

VCP level transmitter, LT-112, failed low 30 minutes ago.

-

I&C is troubleshooting Power Range Nuclear Instrument N-41 because of a

blown fuse.

Which ONE of the following conditions will occur if power is lost to the 1A 42OV AC

Vital Bus?

A. A reactor trip will occur.

B. A boration of the RCS will begin since LCV-2 15D, RWST to CHG PUMP, will open

and LCV-115E, VCT Outlet ISO, will close.

C. Control rods will begin stepping in.

B. A boration of the RCS will begin since LCL/-115B, RWST to CHG PUMP, will open

and LCV-11 5C5

VCT Outlet ISO, will close.

Source: Modified from Farley Bank Question # I 20 VAC-40204FO7

A - Incorrect; A reactor trip would occur id another PRNl channel, other than N-41, had

already been placed in a tripped condition.

.%Waf

B - incwmx$ Valves LCVs 11 5D and E are powered from Aux Safeguards Cabinet B.

C Incorrect; Rods will step out as a result of the boration.

D - Correct; A boration of the RCS will occur since power was lost to la 42OV AC Vital

Bus causing LCV-115i3, RWST to CHG PUMP, to open and LCV-I15C, VCT Outlet

!SO, to close. (Aux Safeguards Cabinet A)

b

41.

A loss of Aux. Building DC power has occurred due to a Station Blackout event that

has lasted for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Offsite power has finally been restored and the lineups

complete for restoring the battery charging lineup.

Which ONE of the following describes the operational implications of the Aux. Building

125 volt DC System?

A. The battery chargers wit1 be unable to carry steady state normal or emergency

loads until its associated battery is charged for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and wilj not be fully

charged for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

B. The battery chargers will be unable to carry steady state normal QF emergency

loads until its associated battery has been fully charged and will not be fully

charged for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

C. The battery chargers will be immediately able to carry steady state normal or

emergency loads while its associated battery is being charged and will not be fully

charged for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

B. The battery chargers will be immediately able to carry steady state normal loads but

unable to carry emergency loads until its associated battery has been fully charged

and will not be fully charged for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

A - Incorrect; Each battery charger is designed to provide adequate capacity to restore

its associated battery to full charge in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the battery has been fully

discharged: while carrying steady state normal or emergency loads.

E) - Incorrect; Each battery charger is designed to provide adequate capacity to restore

its associated battery to full charge in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the battery has been fully

discharged, while carrying steady state normal or emergency loads

C - Correct

D

~ Incorrect; Each battery charger is designed to provide adequate capacity to restore

its associated battery to full charge in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the battery has been fuily

discharged, while carrying steady state normal or emergency loads

-

42.

Unit 1 is at 70% power when the following indications are received:

• Annunciator KC3, 1A OR 1B SGFP TRIPPED

• RPM indicator for I A SGFP rapidly falling

Which ONE of the following describes the required operator actions the operator

should take?

A. Place MAIN TURB EMER TRIP switch to TRIP for at least 5 seconds.

B. Check reactor tripped due to the SGFP trip and go to EEP-0, Reactor Trip and

Safety Injection.

C. Reduce turbine load to less than 540 MW and reduce reactor power to match

turbine power.

D. Check that the AFW pumps auto started.

Source: Farley Exam Bank Question #AOQ-13.0-5252QMO2

References: AOP-23.0

A - Incorrect; This will result in a main turbine trip which is not required since a total loss

of feed has not occurred.

B - Incorrect; A reactor trip will not occur on a loss of a SGFP, unless that loss results in

low SG levels.

C - Correct; Reducing turbine load and reducing reactor power maintains the RCS and

secondary side parameters within the limits for continued plant operation with one

SGFP still operating.

D ~ Incorrect; AFW pumps will start on a total loss of feed.

-.-

43.

A rapid load reduction on Unit 1 to decrease to minimum load from 100% power is in

progress per AOP-17.0, RAPID LOAD REDUCTION. B loss of control oil causes the

1A SGFP to coast down. The operators stopped the load reduction and have entered

AOP-13.0, Loss of Main Feedwater. S/G water levels decreased to approximately 35%

and are now recovering with FRVs in AUTO. The Unit is currently at 50% power and

Turbine load is at about 450 MW.

Which ONE of the following describes the REQUIRED operator actions?

A. Maintain SG levels greater than 35% and verify SG narrow range levels are

maintained less than 75%

B. Maintain S/G level controi in auto, verify proper operation of the feed regulating

valves and verify S/G narrow range levels trending to 65%.

C. When S/G narrow range levels reach approximately 55%, take manual control of

the feed regulating valves and reduce demand to 75% and return to auto, verify

levels trending to 65%.

D. Trip the reactor and go to EEP-0, "Reactor Trip or Safety injection," while

continuing in BOP-I 3, "Loss of Main Feedwater".

A - Incorrect; These are the S/G level valus for the fast load reduction, AOP-17 step 7.

B - Incorrect; This is not the required actions of AOPt3.0.

C- Correct; AOP-13.Q imrnediated action Step I RNO Step 1.5. S/G level recovery

actions when both SGFPs do not trip.

B - Incorrect; This is the action required if the S/G levels do not adequately recover.

-

44.

Que to a complete loss of instrument air, the control room operator tripped the reactor

from 100% power. The turbine-driven auxiliary feedwater (TDAFW) pump auto started.

The motor driven auxiliary feedwater (MDAFW) pumps failed to auto start.

Which ONE of the following describes the action(s), if any, that must be taken and

why?

A. Use the handjack to close HV3235A and HV-32333 in the main steam valve room

(MSVR), to avoid causing an uncontrolled cooldown.

B. Start the emergency air compressors and align to supply the TDAFW pump steam

admission valves to ensure the TBAFW pump will continue to run past 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to

provide an adequate heat sink.

C. No action is required since all valves associated with the TBAFW pump fail open.

D. Use the handjack to apen HV-32358 and HV-3235B in the main steam valve room

(MSVR) to ensure the TDAFW pump will cantinue to run past 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to provide an

adequate heat sink.

A - Incorrect, With only one AFW pump available over cooling should not be a concern.

B - Correct, Per AOP-6.0 Step 9

C - Incorrect, HV-32358 and HV-32358, steam admission valves to the TDAFW pump

in the main steam valve room (MSVR) do not fail open.

B - Incorrect, HV-3235A and HV-3235B in the main steam valve room (MSVR), can

not be jacked open, only jacked closed.

45.

Unit 1 is operating at 100% steady-state reactor power all systems are in automatic

and functioning properly.

- A reactor trip and SI has just occurred.

- A problem in the high voltage switchyard deenergines the 1 B SIU transformer.

- DIG 1 B cannot be started.

- SIG narrow range levels are 'A' 26%, 'B' 45% and '6'

45%.

Which Unit 1 AFW pump@) are running?

A. 'A' MDAFW and TDAFW.

E. 'A'

and 'B' MDAFW.

C. 'B' MLSAFW only.

D. 'A MDAFW only.

Source: Farley 2001 NRC Exam

A - Correct, The TDAFW pump will start on a blackout signal and the A MDAFW pump

will start on SI sequencer. B MDAFW pump does not have power

E? & C - Incorrect, The 5 MDAFW pump does not have a power source.

D - Incorrect, TBAFWP will also start.

...

46.

Unit 1 is at 100% power with 'E? Train on service.

D602, 1G 4160V bus tie to 1L 4160V bus trips.

AOP-20.0 "Loss of Service Water" has been entered.

'A Brain SW pressure is 90 psig, and stable.

'B' Brain SW pressure is 50 psig, and stable.

.--

An attempt to start I C CCW pump was made, and it tripped on overload.

RCP motor bearing temperatures are reading 163'F and slowly rising.

Which ONE of the following describes the actions to be taken in accordance with

AOP-20.0, Loss of Service Water?

A. Trip the reactor and enter EEP-0.0 "Reactor Trip or Safety Injection"

B. Start the 1A charging pump; then stop the I C charging pump.

C. Align 1B CCW pump to 'A' train.

D. Shift the Spent Fuel Pool Cooling trains.

Source: Farley Exam Bank Question #AOQ-I 0.0-5252OJO6 001

Reference: AOP-10.0

A - Incorrect; This is done when RCP motor bearing temps reach 195OF, reference

note describing adequate support in AOP-9.0

B - Incorrect; Same as D. Also, 16 Chg pump has CCW flow even though the CW isn't

being cooled. 1A Chg pump will have no CCW cooling at all

C - Correct; This is done to provide coiling water to the Misc header.

B - Incorrect; Since the A train CCW pump tripped on overload, there is no cooling flow

in that train of CCW, the operator cannot perform this step.

47.

Which ONE of the following describes the NORMAL, EMERGENCY, and ALTERNATE

power supplies to Emergency 416QV A 6 Bus 1 H?

NORMAL

EMERGENCY

ALTERNATE

A.

SIU 1B

1-2A DG

SIU I A

B.

SIU 1A

I C DG

SIU 1B

C.

SIU I A

I&

DG

SIU 1B

D.

SIU 1B

1B DG

SIU ?A

Source: Modified from Farley 2001 NRC Exam.

A - Incorrect, Correct for BUS 1 F.

B - Correct

C - Incorrect, The Normal and Alternate are correct, but the Emergency is incorrect.

8) - Incorrect, This is correct if it was thought that 1 H was B Train.

.. ,

48.

Plant conditions are as follows:

- Unit I is at 95% power.

-

The Unit 1 "B" train battery supply breaker to 1 B I25 VDC auxiliary building bus

is open to jumper out a cell.

-

The supply breaker to 4160 VAC bus 1G trips on fault.

Which ONE of the following describes the expected response to this event?

A. 48 BieseB Generator wilb start, but the output breaker will not close.

B. I B Diesel Generator will start and reenergize the 1 G 4160 VAC bus.

C. Unit 1 reactor trip only wiil occur.

B. Unit 1 reactor trip and safety injection will occur.

Source: Farley Exam Bank Question #DC DIST-52103202 004

Red: SOP-37.0

A -Incorrect; There is no BC power to allow starting of the 1 El BG

B - Incorrect; There is no BC power to allow starting of the 1 B DG

C - Incorrect; A reactor trip will occur due to loss of the Vital AC 'IC and 1 D busses

giving a 2 of 3 trip signal on Bow SIG pressure.

D -Correct; A reactor trip will occur due to loss of the Vital AC I C and 1 D busses giving

a 2 of 3 trip signal on low S/G pressure which also gives an SI.

.

-.

49.

Which ONE of the following is a reason why battery charger IC', the swing battery

charger, for the auxiliary building 125V DC distribution system is key-interlocked?

A. Ensures voltages are matched before closing DC output breakers.

B. Prevent Battery Charger 'C' from carrying BC buses A and B at the same time.

C. Ensure battery charger 'C' output breaker is closed on a dead bus.

8). Provides administrative control when using 'A' train power to supply the 'B' train DC

bus.

Source: Modified from Farley Exam Bank Question #BC DIST-40204E02 007

A - Incorrect; No voltage interlock associated with this key-interlock

B Correct; per OQS-!52?03C

C - Incorrect; No sychroniming circuitry associated with this key-interlock

B -Incorrect; This is the result of using the 'C' battery charger.

50.

Which ONE of the following describes the action(sj required in accordance with

SOP-38.0, Diesel Generators, if the I C or 2C De oil temperature decreases to less

than 200°F AND the keep warm lube oil system is in service (i.e., the circulating oil

pump is running)?

A. The BG is declared inoperable until the oil temperature increases above IOO'F so

the engine can be started immediately.

B. The cylinders shall be blown down and the engine barred over prior to starting the

engine.

C. The jacket water cooling system shall be secured to raise lube oil temperature

above IOO'F.

D. The keep warm lube oil system shall be secured to raise lube oil temperature

above 1 OO'F.

Source: Farley Bank Question #DG-52102104

A - Incorrect; temperature should be raised above 100 OF, but this is not the correct

answer per SOP-38.0.

B - Correct; SOP-38.0 precaution 3.1 3 and caution prior to Step 4.3.8 and OPS-521021

page 34

C - Incorrect; this is not addressed by procedures

D - Incorrect; this is not addressed by procedures

51.

The reactor is at 30% power. For an unknown reason, instrument air pressure is

falling. All available air compressors have been started and pressure continues to fall.

The main feed regulating valve operation has started to become erratic. Feed flow is

decreasing to the Steam Generators, levels are at 60% and slowly decreasing.

Which ONE of the following describes the action(s) the operator should take?

A. Trip the reactor and go to EEP-0.

5. Trip the turbine and ramp the reactor to less than 2% power and establish AFW

flow.

C. Ramp the turbine and reactor to below 5% and establish A W flow.

8. Dispatch operators to manually jack open the main feed regulating valves to control

SG level.

Source: Farley Exam Bank Question #AOP-6.0-52520F08

A - Correct; AOP-6.0 Step 1, WHEN reactor critical AND control of critical AOVs erratic,

THEN trip the reactor and go to EEP-0 REACTOR TRIP OR SAFETY INJECTION.

FRV's are "critical valves.

B - Incorrect; turbine trip is not a priority in AQQ-6 these are the actions of AOP-I3.0,

loss of feedwater.

C Incorrect; ramping down is not an option.

D - Incorrect; not proceduralized, non-conservative, defeats FW Isolation signal.

,

.

\\. ,.

52.

The control room has just been evacuated due to a fire in the cable spreading room.

Which ONE of the following conditions will require the use of reactor head vents to

assist in plant recovery when operating from the Hot Shutdown Panels?

(Assume no Safety Injection signal present)

A. Loss of Reactor Coolant Pumps.

B, Pressurizer level decreasing below 15% level,

C. Steam Generator levels decreasing below 25% level,

B. High Head Safety Injection flow of 225 gpm with RCS pressure at 2235 pig.

Source: Farley 2001 NRC Exam

Original Source: Farley NRC Exam 1998

LO: 052521 604

A - incorrect, Natural circulation can be used following a loss of RCPs.

B - Correct, Pressurizer level decreasing below 15% will result in letdown isolation with

the inability to reopen LCV-459 and bCV-460, requiring the use of the head vents for

removing mass from the RCS.

C - Incorrect, Control of S/G levels is available at the HSPs therefore, control of RCS

cooldown is unavailable.

D - Incorrect, PORV available at this time if desired to lower pressure.

~

._

53.

Concerning the Gaseous Waste Processing System. which ONE of the following is

correct if Unit 'l is in Mode 2, with the monitors required in TR 13.12.1 inoperable?

REFERENCE PROVIDED

A. With oxygen concentration equal to 4% and hydrogen concentration equal to 5% in

a waste gas decay tank, oxygen concentration must be reduced to less than or

equal to 1% prior to Mode 1 entry.

B. With oxygen concentration equal to 3% and hydrogen concentration equal to 5%,

oxygen concentration must be reduced to less than or equal to 1 % within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

However, Mode 1 entry is permitted.

C. With oxygen concentration equal to 5% and hydrogen concentration equal to 2%,

oxygen concentration must be reduced to less than 1 % prior to Mode 1 entry.

B. With oxygen and hydrogen concentrations equal to 5%, actions must be taken

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place Unit 1 in a Mode in which the Tech Spec does not apply

Source: Farley Exam Bank Question #WAST GAS-52106B01 005

References: TRM 13.12.3

A - Incorrect; Does not preclude mode change.

5 - Correct; Per TRM 1312.3

C -Incorrect; Does not preclude mode change.

D - Incorrect; Applicable to all modes

.. .

54.

Which one of the following occurs after receiving a HIGH radiation signal from the

control room ventilation monitor, R-35A?

A. Utility exhaust fan suction dampers (HV-3628 and HV-3629) close.

B. Exhaust fan inlet dampers (HV-3649A, B, C) close.

C. Filtration exhaust and recirculation fans start.

19. Pressurization system supply fans start.

Source: Farley Exam Bank Question #RM§-40305AO7

A - Correct; Per QPS-521Oi'C

E3 - Incorrect; Happens on a T - signal.

C - Incorrect; Happens on a T ~ signal.

D ~ Incorrect; Happens on a T ~ signal.

55.

/Lela cams &6dtz&

W & & G p B r n ad @ @ E x -

~~~a~~

A gaseous waste release is in progress to the vent stack in accordance with a gas

waste permit and SOP-51.1

~ "WASTE GAS SYSTEM GAS DECAY BANK RELEASE."

During the planned waste gas release, the power supply to 8-14 (Plant Vent Gas

Monitor) fails.

Which ONE of the following describes the operator actions?

A. Immediately close RCV-14, Waste Gas Release Valve, to stop the unmonitored

release and inform the Shift Supervisor.

B. Check that RCV-14, Waste Gas Release Valve, closed automatically to prevent any

unmonitored release, notify Chemistry and Health Physics to implement sampling in

accordance with the Offsite Dose Calculation Manual and inform the Shift

Supervisor.

C. Check that RCV-14, Waste Gas Release Valve, closed automatically to prevent any

unmonitored release, secure from the release using SOP-51 .I

and notify l&C

personnel to investigate the failure.

D. Verify RCV-14, Waste Gas Release Valve, is open, verify the last reading on R-24

was below the setpoint, notify Health Physics to implement sampling procedures

and inform the Shift Supervisor.

The radiation monitors fail to a "High Radiation" conditions on loss of instrument andlor

control power that will result in actuation of associated automatic functions.

A - Incorrect; The discharge in progress is automatically securred the auto shutting of

RCV-14.

5 - Correct; The discharge in progress is automatically securred the auto shutting of

RCV-14. Immediate actions of Annunciator FH2, WME CH FAILURE, is to check

indications and notify Chemistry and HP. Immediate actions of Annunciator FHI, RMS

HI-RAD, are Lo verify that RCV-14 closed. Action from precaution in SOP-51.1 is to

secure the discharge and notify Shift Supervisor.

C-+TX#W& , Notifying Instrument Service personnel should occur but is not the

immediate concern.

&l

D - Incorrect; The discharge in progress is automatically securred the auto shutting of

RCV-14.

-

56.

Unit 1 is in the process of starting up and is currently at 25% power.

Unit 1 Circulating water pit level has dropped to 250 feet.

Which ONE of the following describes the process by which water is made up to the

Circulating Water Canal?

A. Service Water is automatically made up to the system via Circulating Water Makeup

Valve (560).

B. Service Water must be manually made up to the system via Circulating Water

Makeup Valve (560).

C. River Water is automatically made up to the system via Circulating Water Makeup

Valve (560).

D. River Water must be manually made up to the system via Circulating Water Makeup

Valve (560).

A - Incorrect; At this low power level the Circuiating Water Makeup Valve (560) will be

controlled in "Remote Manual" not automatic.

B - Correct; Per OPS-52104D

C & D - Incorrect; Service water is the makeup supply to the Circ water canal, river

water is the makeup to the service water system.

57.

Given the following on Unit 1 :

~ 1B DIG is running and the Shift Supervisor has determined that it is required.

- Service Water has been lost to the 1 B DIG and can not be restored.

Which ONE of the following describes when the affected DIG is required to be stopped

IAW AQP-20.0, "LOSS OF SERVICE WATER", and what engineered safeguards

feature (ESF) loads will be lost?

A. As soun as it is determined that SW cannot be restored to protect the DIG from

damage due to overheating and 1A component cooling water (CCW) pump will be

lost.

B. As soon as it is determined that SW cannot be restored to protect the DIG from

damage due to overheating and 1A charging pump will be lost.

C. If the local Lube Oil temperature alarm cannot be maintained clear to protect the

DIG from damage due to overheating and 1A charging pump will be lost.

D. If the local Lube Oil temperature alarm cannot be maintained clear to protect the

DIG from damage due to overheating and l A component cooling water (CCW)

pump will be lost.

Source: Modified from Farley Bank Question #AOP-2 0.0-5252OJO6 002

Ref: AOP-10.0

A - Incorrect; AOP-10 has the operator isolate SW to the TI3 and other components as

well as line-up SW fiow from the other unit first. This is the correct ESF

load that would be lost.

3 - incorrect; AOP-10 has the operator isolate SW to the TB and other components as

well as line-up SW fiow from the other unit first. This is also the incorrect

ESF load that would be lost, I A charging pump is powered from 4160V

1 F bus.

6 - Incorrect; Step 4.2.6 says that if the LO temp alarm cannot be cleared then Stop the

DIG however, this is also the incorrect ESF load that would be lost, 4A

charging pump is powered from 4160V 1 F bus.

D - Correct; Step 4.2.6 says that if the LO temp alarm cannot be cleared then Stop the

DIG. This is the correct ESF load that would be lost since the I A CCW

pump is powered from 41 60V 2 G bus.

-.

58.

Unit 1 is experiencing a loss of instrument air. The crew has entered AOP-6, Loss of

instrument Air.

Which ONE of the following describes the pressure at which V-901, Service air header

isolation valve, closes and when V-903, Instrument air to turbine building isolation

valve, closes as instrument air pressure continues to decrease?

v-901

v-903

A.

80 psig

45 psig

B.

70 psig

45 psig

C.

80 psig

55 psig

83.

45 psig

80 psig

Source: Modified from Farley Bank Questions #COMP AIR-40204B07 002 and COMP

AlR40204D07 003

A - Correct; Per OPS-52108A, V-901 is the first to automatically close at 80 psig and

V-903 is the last to automatically close at 45 psig.

B - Incorrect; V-902, Instrument Air Dryer Bypass Valve, opens at 70 psig.

C - Incorrect; V-904, Instrument Air to Service Building, shuts at 55 psig.

B - Incorrect; V-901 and V-903 values are reversed.

Unit 2 was operating at 100% power when an electrical fire started inside the Cable

Spreading Room.

Which ONE of the following describes what type of fire suppression system is installed

inside the Cable Spreading Room and what are the hazards to personnel if they enter

this room?

A. A deluge manual sprinkler system is installed. An electrical shock hazard exists

due to the use of water to combat an electrical fire.

B. An automatic high pressure C02 system is installed. An asphyxiation hazard exists

due Bo the presence of C02 gas.

C. An automatic Halon system is installed. An asphyxiation hazard exists due to the

presence of Haion gas.

D. A manual low pressure C02 system is installed. An asphyxiation hazard exists due

to the presence of C02 gas.

Source: Modified from Farley Exam Bank Question #FIRE PROT-4O183502

A - Incorrect; Not a manual deluge system

3 - Incorrect; An automatic high pressure CQ2 system not in room

C - Incorrect; No Halon in room

D - Correct; The Cable Spreading Room has a low pressure C02 system.

-.-.

60.

While at 100% power, which ONE of the following conditions represents a loss of

primary containment integrity IAW Technical Specifications?

A. An electrician opens the outer containment airlock door to perform maintenance

activities without prior approval.

B. During an inspection of the equipment hatch, it is determined that the equipment

hatch is not sealed properly.

C. While performing an operability test of two normally open redundant containment

isolation valves, one of the valves fails to close.

B. An operator enters containment but leaves the inner airlock door OPEN.

Source: Farley Exam Bank Question #CTMT SKP&8S-52102AOl 01 Modified Bank

A - Incorrect; One airlock door can be opened at a time, regardless of whether

permission is granted or not.

B - Correct; Maintaining containment operable requires compliance with the visual

inspections.

C - Incorrect; Need only one operable isolation valve in series to retain containment

integrity.

B - Incorrect; One airlock door can be opened at a time and retain containment

integrity.

1-

61.

After a plant trip, the Unit 1 turbine-driven auxiliary feedwater (TBAFW) pump tripped

on overspeed.

The control room operator has isolated steam supplies from the steam lines and placed

the speed demand controller to 0%.

TDAFWP TRIP & THRTL VLV QlNZ2MOV3406 must now be closed.

Which ONE of the following describes how this is accomplished?

A. Locally using local handswitch at hot shutdown panel .

B. Locally using the motor ~ ~ n t r o l

pushbutton on the control panel.

C. Remotely from the BOP using the valve control pushbutton.

D. Locally using the manual handwheel on the valve.

Source: Farley Exam Bank Question #AFW-40201 DO9 006

Reference: SOP-22.0

4.10.1

Close the following valves:

PBAFWP STM SU PP From 1 B SG Q1 N12HV3235Al26

TDAFWP STM SUPP From I C SG Q1N12HV3235B

Set TDAFWP SPEED CONT SIC 3405 TO 0% DEMAND.

Close TDAFWP TRIP & THRTL VLV Q1 N12MOV3406 locally using

manual handwheel on valve.

Reset the overspeed linkage on the TBAFWP.

Open TDAFWP TRIP & THRTL VLV BZN12MOV3406 locally or from

BOP.

Verify TDAFWP TRIP AND TV CLOSED annunciator JG4 is cleared.

4.10.2

4.10.3

4.10.4

4.10.5

4.10.6

A, B, ti C - Incorrect; Per the above exerpt from SOP-22, Version 49.0

D ~ Correct; See above

__

62.

In accordance with AQP-28.2 "Fire in the Control Room", communication with Unit 1

HSD panel A & B during the worst case fire, should be achieved by:

A. Gai-tronics Line I

3. Paxphones

C. Sound powered phones on Unit 1

D. Gai-tronics bine 5

Source: Farley Exam Bank Question #AQQ-28.1/.2-52521 CQ3 003

Ref: AQF-28.2 Attachment 1, Communications.

A - Incorrect; Gaitronics not available at HS5 panels on Unit 1

3 - Correct; All PAX available at HSD panels on Unit 1

C

~ Incorrect; AOP-28.2 provides the guidance for making a plant wide announcement,

but does not establish sound powered communications.

I3 - Incorrect; Gaitronics nut available at HSD panels on Unit 1. Gaitronics line 5 is

dedicated line for emergencies.

63. Question Deleted due to post Examination Comments and Rsview.

Which ONE of the following Mode changes requires at least two (2) mode

determination parameters to change?

(Mode determination parameters are Reactivity Condition (Keff), Rated Thermal

Power, Average Coolant Temperature).

A. Going from Mode 1 to Mode 2.

B. Going from Mode 5 to Mode 4.

6. Going from Mode 3 to Mode 2

B. Going from Mode 5 to Mode 6.

Reference Technical Specification Definitions Table 1 .I

- 4

Distractor Analysis:

A: Incorrect, Difference between Mode 1 and Mode 2 requires only % Rated Thermal

Power to change.

3: Incorrect, Difference between Mode 5 and Mode 4 requires only Average Coolant

Temperature to change change..

C: Incorrect, Difference between Mode 3 and Mode 2 requires only Reactivity Condition

(Keff), to change.

B: Correct, Difference between Mode 5 and Mode 6 requires both Reactivity Condition

(Keff), and Average Coolant Temperature to change.

-

64.

Which one of the following is considered a Temporary Plant Alteration that supports

Maintenance per AP-I 3, "Controi of Temporary Alterations?"

A. Placement of a plant labeling deficiency tag IAW AP-25, "Equipment Identification."

B. Lifting leads to defeat a MCB annunciator in preparation for repairs by the

oncoming team.

C. Installation of tygon tubing on a pump drain line IAW AP-14, '"Safety Tagging."

D. Gagging of a relief valve in preparation for a hydrostatic test of that system.

Source: Farley 2001 NRC Exam

A -Incorrect, er AP-13, not a listed item

B

~ Correct, & hen lifting leads for corsective/preventive maintenance or troubleshooting

purposes, the leads shail be identified as shown on the electrical drawing. If the leads

are to remain lifted while not attended by the 'ourneyman or if the job is to be turned

over to another crew, then a temporary identikcation tag shall be placed on each lead

lifted. (AP-13)

C

D

&eeN

.u

65.

AR individual has requested a Restricted Removal (RR) tag order to ailow performance

of a maintenance task that he has been assigned.

Which ONE of the following positions, at a minimum, must the individual hold in order

to mark the RR block on the Tag Order Acceptance section of the cover sheet for a

maintenance task?

A. A designated operator.

B. A tagging official

C. An apprentice.

D. A journeyman.

Source: Farley 2001 NRC Exam

Original Source: Farley Exam Bank Question #052303602003

B

~ Correct, See FNP-Q-AP-14, section 4.2

-.

.

66.

-

Plant conditions are as follows:

Unit 1 is in Mode 1.

The 1B Charging Pump is aligned to 'A' Train and the I C Charging Pump is

operating.

The 4A Charging Pump has been declared INOPERABLE and taken out of

service for oil replacement.

All other portions of the CVCS and related subsystems are OPERABLE.

Which one of the following statements describes the action of the Shift Support

Supervisor - Plant in regard to the LCO Status Sheet for the 1A Charging Pump

condition?

A. NO LCO Status Sheet is required to track the 1A Charging Pump condition.

B. An ABMENISTRATIVE LCO status sheet should be initiated to track the 1A

Charging Pump condition.

C. A VOLUNTARY LCO status sheet should be initiated to track the 1A Charging

Pump condition.

B. A MANDATORY LCO status sheet should be initiated to track the I A Charging

Pump condition.

Source: Farley Bank Question #INTRO TS-52302808 002

B

~ Correct; OPS-52302A states that equipment removed from service that is not

required in the present plant mode but is required in a higher plant mode or if it reduces

the redundancy of the equipment, but not less than T.S. requirements, then an

Administrative LCO may be written. The inoperability of one charging pump reduces

the redundancy of the equipment, but not less than T.S. requirements therefore, an

Administrative LCO should be written to track the I A charging pump condition.

67.

__

In accordance with 1OCFR20, which ONE of the following sets of conditions represent

the LOWEST radiation conditions that would cause an area to be classified as a High

Radiation Area?

Any area accessible to personnel that would result in an individual receiving a dose

equivalent of __ in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 centimeters from the radiation source external to the

body.

A. 0.02 rem

B. 0.05 rem

C. 0.2 rem

B. 0.5 rem

Source: Kewaunee Exam 1211 8/97

REFERENCE: 10CFR20 1003

High Radiation area is any area accessible to individuats, in which radiation levels from

radiation sources external to the body could result in an individual receiving a dose

equivalent in excess of 0.1 rem in 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30 centimeters from the radiation source.

Very High Radiation area is any area accessible to individuals, in which radiation levels

from radiation sources external to the body could result in an individual receiving an

absorbed dose in excess of 500 rads in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 1 meter from the radiation source.

Distracter A - Incorrect, question asks LOWEST radiation conditions that would cause

an area to be classified as a High Radiation Area. 0.02 rem is below 0.1 rem.

Distracter 3 - Incorrect, question asks LOWEST radiation conditions that would cause

an area to be classified as a High Radiation Area. 0.05 rem is below 0.1 rem.

Answer C - Correct, Although higher than the 0.1 rem, it is the lowest that would be

posted as a High Radiation Area.

Distracter D ~ Incorrect, 0.2 rem is lower than 0.5 rem.

.._

68.

Which ON of the following describes the general practice prescribed by the Health

Physics Manual, FNP-0-M-001, that should

be used to minimize the intake of

radioactive material by personnel entering Airborne Radioactivity Areas?

A. Reduction in working times.

3. Increased radiological surveillances.

C. Use of respiratory protective equipment.

D. Reduce airborne levels using engineering controls.

Source: Farley 2000 NRC Exam

A, Ea, 6 - Incorrect; When impractical to apply process or other engineering controls,

other precautionary measures may be used, e.g. increased radiological suveiliances,

reduction in working times, or use af respiratory protective equipment.

B - Correct; As a genefal practice, the plant staff will use process or other engineering

controls to limit the concentrations of radioactive materials in the air below the limits

defined in 10CFR20.

-

~

69.

Which ON of the following is required to be operable by Post Accident Monitoring

Instrumentation Technical Specification in Mode 3?

A. Containment Temperature.

B. AFW flow rate.

C. Accumulator level.

B. Spent Fuel Pool Level.

Source: Modified from Farley Exam Bank Question #POST LOCA-52102BOI OQ2

Reference: Tech Spec 3.3.3

B - Correct; per TS Table 3.3.3-1

78.

Plant conditions are as follows:

--

• Unit I is operating at 100% power.

• Containment air particulate radiation monitor R-I 1 detector is out of service for

repairs; expected return to service in 4 days.

Grab samples are being taken per the Technical Specification action

statement.

Containment Radioactive gas monitor R-1% has just started indicating an

increasing trend in containment atmosphere gaseous radioactivity levels.

Which ONE of the following actions is required and the reason for taking the action?

A. Within an hour, initiate action to place the plant in Hot Standby within 6 additional

hours, to meet Technical Specifications.

B. Enter AOP-1 .O, RCS Leakage, to identify and isolate the source of leakage.

C. Immediately trip the reactor and enter EEP-0, Reactor Trip or Safety Injection, to

mitigate the condition.

D. Immediately initiate a non-emergency notification per ? OCFR50.72, One Hour

Report, to inform the NRC.

Source: Farley Exam Bank Question #AOP-1.0-52520A02 070

A - Incorrect; The indications given do not support a Tech Spec shutdown.

5 Correct; 8-72 is an eariy indication of a primary leak and should be investigated per

AOP-1.

6 - Incorrect; A reactor trip is not warrented at this point from the indications given.

D - Incorrect; Indications given do not indicate that any deviation from the plant's

Technical Specifications exist.

"%.*

71.

A failed open spray valve that could not be shut resulted in a safety injection.

The reactor coolant pump in the affected loop was tripped and, with pressurizer

pressure now under control, safety injection termination was permitted.

With only one charging pump running, pressurizer pressure remained stable.

At the procedural step when normal charging was established, BRZR level started

trending down from 15% level and could not be controlled.

Which ONE of the following describes the actions the operator should take at this

point?

A. Manually SI and recommend transitioning to EEP-0, Reactor Trip or Safety

Injection.

5. Realign HHSl flow; start additional charging pumps, and recommend transitioning

to EEP-0, Reactor Trip or Safety Injection.

C. Realign HHSl flow, start additional charging pumps, and recommend transitioning

to EEP-I, Loss of Reactor or Secondary Coolant.

B. Realign HHSl flow; start additional charging pumps, and recommend transitioning

to ESP-1 2,

Post LOCA Cooldown and Depressurization.

Source: Farley xam Bank Question #ESP-I .1-52531 06 005

References: ESP-1 .I

A - Incorrect; If PZR level can not be maintained, the flow path must be reestablished

and a transition to ESP-I .2 is warrented. There is no need to manually SI and

transition to EEP-0.

B - bncorrect; The transition to EEP-0 is incorrect.

C - Incorrect; The transition to EEP-1 is incorrect.

D - Correct; From ESP-1 .I,

SI Termination, if PZR level can not be maintained, the flow

path must be reestablished and a transition to ESP-1.2 is warrented.

-

72.

Given the following:

..

,

..#

- A Main Steam line Break has occured inside containment on Unit 1.

~

Containment pressure is at 5.5 psig.

- The Crew has entered FWP-P.l, Response to Pressurized Thermal Shock

- An RCS pressure reduction is in progress.

~

The 80 observes RCS Subcooling at 40'F.

Conditions.

Which ON of the following describes the correct action to be taken by the crew?

A. Start an additional charging pump to raise RCS subcooling.

3. Close the P O W to stop RCS depressurization until subcooling is recovered.

C. Continue with the depressurization of the RCS.

B. Bump steam from an intact SIG to raise subcooling.

Source: Modified from Farley Exam Bank Question #2305. Modified to have the steam

leak inside containment, and adverse numbers applicable.

A - Incorrect; starting an additional charging pump will raise RCS pressure, and

increase subcooling, however a pressure increase is not desired.

B - Correct; with adverse containment numbers, and this value of subcooling, the

procedure directs closing the PORV and allowing subcooling to rise.

C ~ Incorrect; with adverse containment numbers and subcooling e 45 OF, the

procedure directs closing of the PORV.

B - Incorrect; a large cooldown has already occurred, and no further cooldown is

allowed until after a soak has taken place.

73.

-

iv

During a small break Loss Of Coolant Accident (LOCA) on a cold leg, when there is not

a large amount of injection flow from the ECCS through the core and out the break, a

phase is reached where the vessel level continues to decrease below the hot leg

penetrations and boiling in the core is the means of transporting the core heat to the

bubble. A fixed differential pressure exists between the core and the break and is

maintained by the loop seal.

Which ONE of the following describes the primary mechanism for heat removal during

this phase?

A. Condensation of vapor from the bubble at the hot leg side of the SIG U-tubes,

which is cooled by SIG water, end then drains back down to the core via the hot

legs.

B. Condensation of vapor in the head, which is cooled by fans in containment, and

then drains back down to the core.

C. Slug flow via the cold legs through the loop seal and flashing across the cold leg

break.

D. Condensation of vapor from the bubble at the cold leg side of the S/G U-tubes,

which is cooled by SIG water, and then drains back down to the core via the cold

legs.

Source: Farley 200 'I NWC Exam

Original Source: Byron 2000-301

A - Correct, This describes REFLUX cooling which is almost as efficient as two phase

natural circulalian.

B

~ Incorrect, The cooling provided Rear is basically losses to ambient and is not very

effective.

C - Incorrect, Not likely to occur on a small break LOCA.

D - Incorrect, Natural circulation can not occur when level in the core has decreased

below the hot leg penetrations.

74.

-

Given the following:

- Unit 4 has tripped from 100% power due to a Loss of Coolant Accident (LOCA)

with a loss of Offsite Power.

- 1-24 Diesel Generator is tagged out.

- I C Diesel Generator has failed to start.

The Operators are performing EEP-1 "Loss of Reactor or Secondary Coolant" and are

at the step to "Verify cold leg recirculation capability - Available".

- WCS pressure is 700 psig.

- AI! SiG pressures are stable at 900 psig.

- WWST level is 12.8 ft. and decreasing slowly.

- I

B RHR Pump has tripped on overcurrent.

- Containment pressure peaked at I O psig and is decreasing.

Waste Gas Processing Room Sump Pumps are running.

- Ail other equipment is operating normally.

The operators should transition to which ONE of the following procedures?

A. ESP-1.2, "Post LOCA Cooldown and Depressurization"

B. ESP-1.3, "Cold Leg Recirculation"

C. ECP-I .I

~ "LQSS of Emergency Coolant Recirculation"

D. ECP-I 2, "LOCA Outside Containment"

Source: New

Reference ECP-1 .I,

A - Incorrect; transition to ECP-1 .I

is required per step 14 of EEP-1 based on inability to

verify cold leg recirc capability

3 = Incorrect; Transition to ESP1 .3 is based on RWST levle of 12.5 ft.

C - Correct; based on inability to verify cold leg recirc capability

B - Incorrect; Transition to ECP-1.2 based on Aux Bldg sump pumps running occurs

after the transition to ECP-4.1.

75.

Given the following conditions:

~ A LOCA has occurred on Unit 1. EEP-I .Q "Loss of Reactor or Secondary

- EE2, CTMT PRESS HI-2 ALERT annunciator alarms

- Containment Pressure is 17 psig.

- Containment High Range Radiation bevel Monitors indicate: R27A is 4 WHR; and

Coolant", is in progress.

8278 is 5 WHR.

Which ONE of the following FRQs is now applicable?

A. FRP-2.1, "Response to High Containment Pressure" due to an RED path based on

containment pressure.

B. FWP-Z.3, Response to High Containment Radiation Level, due to an ORANGE path

based on containment pressure.

C. FRP-2.1, Response to High Containment Pressure, due to an ORANGE path based

on containment pressure.

8. FWP-Z.3, Response to High Containment Radiation Level, due to a YELLOW path

based on high containment radiation.

Source: Fartey Exam Bank Question 52530808 016 Modified.

A - Incorrect; a red path occurs at 54 psig.

B - Incorrect; an orange path does not exist for containment radiation.

C - Incorrect; an orange path for containment pressure is 27 psig.

D - Correct; FRP-Z.3 would be entered on a yellow path based on containment

radiation.