ML20206M004
| ML20206M004 | |
| Person / Time | |
|---|---|
| Issue date: | 05/11/1999 |
| From: | Debra Mccain NRC (Affiliation Not Assigned) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9905140162 | |
| Download: ML20206M004 (71) | |
Text
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UNITED STATES '
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2068H001
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(
l May 11,1999 i
l NOTE TO:
Document Control Desk l
FROM:
Debbie McCain, Licensing Assistant
. Operator Licensing and Human Performance Section
. Operator Licensing, Human Performance
& Plant Support Branch Division of Inspection Program Management, NRR
SUBJECT:
APRIL 1999 GENERIC FUNDAMENTALS EXAMINATION (GFE)
'I Enclosed please find the April,' 1999 GFE examination and answer key to be l
placed in the PDR. ' If you have any questions I can be contacted at 415-1065.
Enclosure:
As stated pf0 i
9905140162 990.511
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-O PDR 4
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UNITED STATES NUCLEAR REGULATORY COMMISSION PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION i
APRIL 1999 - FORM A f
i
)
Please Print 1
Name:
Facility:
)
Docket No.:
Start Time:
Stop Time:
INSTRUCTIONS TO APPLICANT Answer all the test items using the answer sheet provided. Each item has equal point value. A score of at least 80% is required to pass this portion of the written licensing examination. All examination papers j
will be collected 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> after the examination starts. This examination applies to a typical pressurized l
water reactor (PWR) power plant.
SECTION QUESTIONS
% OF TOTAL SCORE COMPONENTS 1 - 44 REACTOR THEORY 45 - 72 THERMODYNAMICS 73 - 100 TOTALS 100 All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature 1
E I
RULES AND GUIDELINES FOR THE l
GENERIC FUNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:
NOTE:
The generic term " control rod" refers to the length of neutron absorber material that can be positioned by the operator to change core reactivity.
1.
Print your name in the blank provided on the cover sheet of the examination.
2.
Fill in the name of your facility.
3.
Fill in your individual docket number.
4.
Fill in your start and stop times at the appropriate time.
5.
Two aids are provided for your use during the examination:
(1)
An equations and conversions sheet contained within the examination copy, and (2)
Steam tables provided by your proctor.
6.
Place your answers on the answer sheet provided. Credit will only be given for answers properly marked on this sheet. Follow the instructions for filling out the answer sheet.
7.
Scrap paper will be provided for calculations.
8.
Cheating on the examination will result in the automatic forfeiture of this examination. Cheating i
could also result in severe penalties.
9.
Restroom trips are limited. Only ONE examinee may leave the room at a time. In order to avoid the appearance or possibility of cheating, avoid all contact with anyone outside of the examination room.
I 10.
After you have completed the examination, sign the statement on the cover sheet indicating that the work is your own and you have not received or been given any assistance in completing the examination.
I 1.
Turn in your examination materials, answer sheet on top, followed by the examination booklet, then examination aids - steam table booklets, handouts and scrap paper used during the examination.
4 i
l 12.
After turning in your examination materials, leave the examination area, as defined by the proctor.
i If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeited.
n GENERIC FUNDAMENTALS EXAMINATION EOUATIONS AND CONVERSIONS HANDOUT SHEET EOUATIONS D = rhc AT P=Pl0WRO) o p
D=rhAh P = P e"")
o
)
^"^
Q = UAAT CRw = S/(1 - K rr) e Q = s"3*' "
CR (1 - K,,n) = CR (1 - K rr2) i 2
e 2
AT = rh 1/M = CR /CRx 3at cire i
2 K,,, = 1/(1 - p)
A = nr
. p = (K rr - 1)/K r F = PA e
er SUR = 26.06/r s = pAV T=b~P W
= M Pu Aerr P E = IR p.
g p=+I+AT T
err Eff. = Net Work Out/ Energy In l' = 1 x 10~' seconds u(P - P ) + (V * - V ') + g(z2 - zi) = 0 2
i 2
i 2g, g,
l A r = 0.1 seconds" ct 2
Se = 32.2 lbm-ft/lbf-sec 3
2 DRW u 9,;p/9,y 1
l CONVERSIONS i
6 1Mw = 3.41 x 10 Btu /hr 1 Curie = 3.7 x 10dps 1
3 1 hp
= 2.54 x 10 Btu /hr 1 kg 2.21 lbm
=
1 Btu = 778 ft-lbf I gal.,,,, = 8.35 lbm C
= (5/9)( F-32)
I ft',,,,,
7.48 gal
=
- F
= (9/5)(*C) + 32 t
I L
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A L
l QUESTION:
1 l
TOPIC:
191001 l
KNOWLEDGE: Kl.02 l
QID:
P1504 (Rev) l Vessels A and B are identical except that vessel A receives overpressure protection from an l
installed relief valve. Vessel B has an installed safety valve. The relief valve and safety' valve have the same pressure set point and design flow rate.
Water is continuously added to each vessel at the same rate (50% of the design flow rate of the j
relief / safety valve). After vessel pressure reaches the set point for each valve, vessel A pressure will and vessel B pressure will A. stabilize slightly above the pressure setpoint; stabilize slightly above the pressure setpoint B. stabilize slightly above the pressure setpoint; vary above and below the pressure setpoint C. vary above and below the pressure setpoint; stabilize slightly above the pressure setpoint D. vary above and below the pressure setpoint; vary above and below the pressure setpoint i
ANSWER: B.
QUESTION:
2 TOPIC:
191001 KNOWLEDGE: K1.03 QID:
P1302 (B15)
When comparing a 3-inch gate valve to a 3-inch globe valve in the same application in an operating cooling water system, if both valves are fully open, the gate valve produces the head loss and the flow rate.
A. smaller; larger B. smaller; smaller C. larger; larger l
D. larger; smaller I
L ANSWER: A.
I p
p L
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A
' QUESTION:
3 TOPIC:
191001 j
KNOWLEDGE: Kl.05 QID:
P403 (Rev)
When manually closing a motor-operated valve, why must the operator avoid using excessive j
valve seating force?
l A. The valve motor may trip on overload during subsequent automatic operation.
B. The valve actuator clutch may be damaged and disable subsequent automatic operation.
l C. The valve stem limit switches may be damaged and cause inaccurate remote valve position indication.
l D. The valve actuator position indicator may be damaged and cause inaccurate local valve l
position indication.
ANSWER: A.
QUESTION:
4 TOPIC:
191001
. KNOWLEDGE: Kl.08 l
QID:
NEW l
When comparing ball valves with butterfly valves, valves are generally more leak tight in 1
I high pressure applications and valves generally exhibit the lowest system pressure drop when fully open.
A. ball; butterfly j
B. ball; ball j
l C. butterfly; butterfly l
D. butterfly; ball ANSWER: B.
1 l
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
5 TOPIC:
191002.
KNOWLEDGE: Kl.02 QID:
P2005 (Rev)
A main steam flow rate measuring instrument uses a steam pressure input to produce main steam flow rate indication in Ibm /hr. Assuming volumetric steam flow rate does not change, a steam pressure decrease will cause indicated steam flow rate to:
A. decrease because the density of the main steam has decreased.
B. increase because the specific volume of the main steam has increased.
C. remain the same because steam pressure does not affect the mass flow rate of main steam.
D. remain the same because the steam pressure input compensates for changes in steam pressure.
ANSWER: A.
QUESTION:
6 TOPIC:
191002 KNOWLEDGE: Kl.05 QID:
P2306 (Rev)
A venturi is used to measure flow rate in a cooling water system. As the water flows from the inlet to the throat of the venturi, water pressure will and volumetric flow rate will (Assume water is incompressible.)
A. increase; remain the same B. increase; increase C. decrease; remain the same D. decrease; increase ANSWER: C.
L.
s J
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
7-TOPIC:
191002 KNOWLEDGE: Kl.05 QID:
NEW A differential pressure detector is being used with an orifice plate to measure water flow rate through a pipe. When the flow detector was last calibrated, the following parameters were observed:
Upstream Pressure:
125 psig Actual Flow Rate:
100 gpm Downstream Pressure: 116 psig Indicated Flow Rate:
100 gpm Significant erosion of the orifice hole has occurred since the calibration such that actual flow rate through the orifice has increased to 120 gpm while the upstream and downstream pressures have changed to 110 psig and 106 psig respectively.
1 What is the approximate currently indicated flow rate?
A. 44 gpm B. 67 gpm C. 81 gpm D. 120 gpm ANSWER: B.
PROOF:
l Flow VA Pi
=
Flow 2 JA P 2 l
100 8
3 di =
2-l
=
x 66.7 g p m x =
i
! I
f USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
8 TOPIC:
191002 l
KNOWLEDGE: Kl.10 QID:
P413 (B410)
If the pressure sensed by a bourdon tube increases, the curvature of the detector will because of the greatest force being applied to the curve of the detector.
l
. A. increase; outer B. increase; inner C. decrease; outer D. decrease; inner ANSWER: C.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A
- QD.3 TION:
9 TOPIC:
191002 KNOWLEDGE: Kl.06 QID:
P2308 (Rev)
Refer to the drawing of a steam generator (S/G) differential pressure (D/P) level detector (see figure below) that has been calibrated at the current S/G pressure of 400 psia.
A reactor coolant system heatup has resulted in an increase in S/G pressure from 400 psia to 900 psia over 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Without density compensation of the level instrumentation, at the end of the heatup S/G level indication would indicate than actual level because the density of the water in the has changed significantly.
A. higher; steam generator B. higher; reference leg C. lower; steam generator D. lower; reference leg ANSWER: C.
,' STEAM conoEnsino Vf l
3 E0ng 7p. ATE./
/
YA DETECTOR l
STEAM GENERATOR DIFFERENTIAL PRESSURE LEVEL DETECTOR
! l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
10 TOPIC:
191002 KNOWLEDGE: Kl.12 QlD:
P1011 A properly calibrated 0 to 100 psia diaphragm pressure detector is connected to a pressurized system; the low pressure side of the' detector is vented to the atmosphere. The detector is currently producing a system pressure indication of 75 psia.
If the detector diaphragm ruptures, indicated pressure will be approximately:
A. O psia.
B. 15 psia.
C. 60 psia.
D. 100 psia.
ANSWER: B.
PROOF:
75 psia
-O-15 psia (atmosphere)
Diaphragm rupture - System pressure not seen.
With diaphragm pressure detector equalized with atmosphere, indicated pressure would be atmospheric or 15 psia.
QUESTION:
11 TOPIC:
191002
. KNOWLEDGE: Kl.13 QID:
Pl510 (B309)
In contrast to a thermocouple, a resistance temperature detector:
A. is used in high temperature applications.
B. does no_t require an external power supply for temperatur" i lication.
I C. uses a single type of metal in the sensir.sement, j
i D. is commonly placed in direct contact with the monitored substance.
i ANSWER: C.
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l L-
I t
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A L
QUESTION:
12 l
TOPIC:
191002 KNOWLEDGE: Kl.16 QID:
P813 (B812)
What is the most common type of position sensor used to provide remote indication of a valve that is normally fully open or fully closed?
A. Reed switch B. Limit switch C. Servo transmitter D. Linear variable differential transfonner ANSWER: B.
QUESTION:
13 TOPIC:
191002 KNOWLEDGE: Kl.17 QID:
P1910 (Rev)
A plant startup is in progress immediately following a reactor refueling. The external nuclear instrumentation (NI) was calibratedjust prior to the refueling shutdown and has not been readjusted.
If power level is stabilized at 90%, NI power level will be than actual power level because, compared to pre-shutdown 90% power level operation, A. higher; power production in the outer portion of the core has increased B. higher; total core neutron production rate has increased I
C. lower; power production in the outer portion of the core has decreased D. lower; total core neutron production rate has decreased ANSWER: C. i l
[
{
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
14 TOPIC:
191002 KNOWLEDGE: Kl.18
.QID:
P1213 Which one of the following describes why a BF proportional counter can be used in the source 3
range to measure neutron radiation in a radiation field that also contains gamma radiation?
A. Neutrons directly ionize the BF gas, producing larger pulses than gammas.
3 B. Neutrons interacting with the BF gas result in the release of alpha particles which produce 3
larger pulses than gammas.
J C. Neutrons are captured by boron-10 and produce additional neutrons that completely ionize the fill gas in the detector.
D. The gamma radiation field is insignificant when compared to the neutron field, ANSWER: B.
QUESTION:
15 TOPIC:
191003 KNOWLEDGE: Kl.05 QlD:
P1217 (B1416)
The purpose of a typical valve positioner in a pneumatic control system is to:
A. convert an electrical signal to an equivalent air pressure.
B. position the solenoid valve that supplies air to the valve actuator.
C. provide valve position feedback to the valve controller to develop a setpoint error and adjust valve actuator air supply pressure to position the valve.
D. compare valve controller output signal to valve position and adjust valve actuator air supply pressure to position the valve.
ANSWER: D.
r i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A i'
l l
QUESTION:
16 TOPIC:
191003-KNOWLEDGE: Kl.04 QID:
Pl715 (B1914)'
l Refer to the drawing of a lube oil temperature control system (see figure below).
Which one of the following describes the type of control used in the lube oil temperature control system?
A. Open loop because lube oil temperature feedback is provided to the controller from the lube oil temperature transmitter B. Open loop because lube oil temperature is being controlled by positioning a flow control valve in a separate system C. Closed loop because lube oil temperature feedback is provided to the controller from the lube oil temperature transmitter D. Closed loop because lube oil temperature is being controlled by positioning a flow control valve in a separate system i
k ANSWER: C.
l a
ER L
==e _______ @
l i
i mr
=m
==
a" i
LUBE Cil TEMPERATURE CONTROL SYSTEM j
l 1
1 l
! l
USNRC GENERIC FUNDAMENTALS EXAMINATION
[
APRIL 1999 PWR - FORM A Y
QUESTION:
17 TOPIC:
191003 KNOWLEDGE: Kl.05 QID:
P2116 (Rev)
~
An air-operated isolation valve requires 2,400 lbf applied to the top of the actuator diaphragm to open. The actuator diaphragm has a diameter of 12 inches.
If control air pressure to the valve actuator begins to increase from 0 psig, which one of the l
following is the approximate air pressure at which the valve will begin to open?
A. 21 psig B. 34 psig C 43 psig D. 64 psig ANSWER: A.
PROOF:
F=PxA z
2 P = F/A = 2400 lbf/113 in = 21.2 lbf/in QUESTION:
18 TOPIC:
191003 KNOWLEDGE: Kl.06 QID:
P1818 (Rev)
A diesel generator is supplying an isolated electrical bus with the governor operating in the isochronous mode if a large electrical bus load trips, generator frequency will:
A. initially increase, then decrease and stabilize below the initial value.
B. initially increase, then decrease and stabilize at the initial value.
C. initially increase, then decrease and stabilize above the initial value.
D. remain constant during and after the load trip.
l ANSWER: B.
l I 4
p i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
19 TOPIC:
191003-KNOWLEDGE: Kl.09 QID:
NEW The temperature of the water in a small outside storage tank is controlled by a set of heaters submerged in the tank. The heaters energize at a water temperature of 40*F and deenergize at 48 F. When the heater set is energized, the tank heatup rate averages 2*F/ minute in the operating range between 40 F and 48 F.
Which one of the following types of control devices is used in the heater control circuit to produce these characteristics?
A. Bistable B. Proportional C. ProportionalIntegral D. Proportional Derivative ANSWER: A.
QUESTION:
20 TOPIC:
191004 KNOWLEDGE: Kl.07 QID:
P1924 (Rev)
A constant-speed centrifugal pump motor draws the most current when the pump is:
A. at maximum rated flow conditions.
B. operating at runout flow.
1 C. accelerating to normal speed during start.
D. at shutoff head with no recirculation flow.
ANSWER: C.
! 4 I
1 USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
21 TOPIC:
191004 KNOWLEDGE: Kl.06 QID:
P1521 (B1918)
Refer to the drawing of a cooling water system (see figure below).
The available net positive suction head for the centrifugal pump will be decreased by:
A. opening surge tank makeup valve "A" to raise tank level.
B. throttling heat exchanger cooling water valve "B" more open.
l C. throttling pump discharge valve "C" more open.
I D. reducing the heat load on the cooling water system.
ANSWER: C.
A COOUNG A
SURGE WATER MAKEUP >
TANK HEAT g
EXCHANGER w
b)"
11 O LJ F1 tJe!S C
A D
-A O
PUMP' COOUNG WATER SYSTEM r
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A L
l QUESTION:
22 l
TOPIC:
191004 KNOWLEDGE: Kl.12 QID:
Pl721 (B1024).
Refer to the drawing of a centrifugal pump operating curve (see figure below).
Which point represents pump operation at runout conditions?
A. Point A B. Point B C. Point C D. Point D ANSWER: C.
POINT A
/
PUMP POINT B HEAD POINT D POINT C
./
FLOW CENTRIFUGAL PUMP OPERATING CURVE i
I i
l l
l 1
l i
i
+
1 USNRC GENERIC FUNDAMENTALS EXAMINATION i
APRIL 1999 PWR - FORM A QUESTION:
23 TOPIC:
191004 KNOWLEDGE: Kl.14 QID:
P623 (Rev)
Refer to the drawing of a lube oil temperature control system and the associated centrifugal pump operating curve (see figure below).
If the pump is operating at point B on the operating curve, how will the operating point change if the temperature controller setpoint is decreased by 10 F?
A. Operating point B will be located on curve I closer to point E.
B. Operating point B will be located on curve I closer to point D.
C. Operating point B will be located on curve 2 closer to point A.
D. Operating point B will be located on curve 2 closer to point C.
ANSWER: D.
l
= ". "
'r' o
=
______ 4 h
s O_
1,
==
LUBE OIL TEMPERATURE CONTROL SYSTEM f omYa P
Ponte CUutyt t PowfS nm j
PousY 6 PLost CENrRIFUGAL PUMP OPFRATING CURVE l
h.
' USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A i
QUESTION:
24 TOPIC:
191004 i
KNOWLEDGE: Kl.09 QID:
P2223 (B1021)
A centrifugal pump is operating in parallel with a positive displacement pump in an open system.
Each pump has the same design pressure.
If pump discharge pressure increases to the maximum design pressure of each pump, the centrifugal pump will be operating at flow and the positive displacement pump will be operating at flow.
A. minimum; minimum B. minimum; rated C. rated; minimum D. rated; rated l
ANSWER: B.
l i
l b
USNRC GENERIC FUNDAMENTALS EXAMINATION i
APRIL 1999 PWR - FORM A
)
. QUESTION:
25 TOPIC:
191004 KNOWLEDGE: Kl.16 l
QID:
P1725 (B1722) l L
A typical single-stage radial-flow centrifugal pump is being returned to service following maintenance on its ac motor. Which one of the following will occur when the pump is started if two of the three motor power leads were inadvertently swapped during restoration?
A. The motor breaker will trip on overcurrent.
B. The motor will not turn and will emit a humming sound.-
C. The motor will rotate in the reverse direction with reduced or no flow rate.
D. The motor will rotate in the normal direction with reduced flow rate.
1 ANSWER: C.
QUESTION:
26 TOPIC:
191004 KNOWLEDGE: Kl.22 QID:
P1026 (Rev)
Which one of the following conditions will result in the greatest increase in volumetric flow rate in a water system with one positive displacement pump operating at 400 rpm and a discharge pressure of 100 psig? -
1 A.- Increasing pump speed to 700 rpm B. Decreasing pump discharge pressure to 40 psig C. Starting a second identical positive displacement pump in series with the first D. Starting a second identical positive displacement pump in parallel with the first
- ANSWER:- D.
l _
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
27 TOPIC:
191005 KNOWLEDGE:. Kl.02
'QID:
P1028 (B1526)
Which one of the following will result from prolonged operation of ac motor windings at excessively high temperatures?
A. Decreased electrical current demand due to reduced counter electromotive force B. Decreased electrical ground resistance due to breakdown of winding insulation C. Increased electrical current demand due to reduced counter electromotive force D. Increased e.lectrical ground resistance due to breakdown of winding insulation ANSWER: B.
QUESTION:
28
. TOPIC:
191005 KNOWLEDGE: Kl.03 QID:
P2027 (Rev)
A diesel generator (D/G)is supplying both KW and KVAR to an electrical bus in parallel with the grid. Assuming bus voltage does p_ot change, if the D/G voltage regulator set point is decreased slightly, then D/G KW will and D/G amps will A. remain the same; decrease
- B. remain the same; remain the same C. decrease; decrease D. decrease; remain the same ANSWER: A.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
29 TOPIC:
191005 KNOWLEDGE: Kl.04 QID:
P2329 (Rev)
A multispeed centrifugal pump is operating with a flow rate of 1800 gpm at a speed of 3600 rpm.
Which one of the following approximates the new flow rate if the pump speed is decreased to 2400 rpm?
A.- 900 gpm B. 1050 gpm 4
C. 1200 gpm D. I350 gpm ANSWER: C.
PROOF: p,3 F
S 2
2k S F' 2
F2*
S i p, 2400(1800) 3600 F = 1200 gpm 2,-
r-l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
30
. TOPIC:
191005 KNOWLEDGE: Kl.01 QID:
P1427
- A plant is operating at full power when a reactor coolant pump experiences a locked rotor. How will pump ammeter indication respond?
A. Decreases immediately to zero due to breaker trip B. Decreases immediately to no-load motor amps C. Increases immediately to many times running current, then decreases to no-load motor amps D. Increases immediately to many times running current, then decreases to zero upon breaker trip ANSWER: D.
QUESTION:
31 TOPIC:
191005 KNOWLEDGE: Kl.06 QlD:
P30 (Rev)
Frequent starts of large motors will result in overheating of the motor windings due to high current flow caused by:
A. Iow electrical resistance of the motor windings.
I B. an electrical short circuit between the rotor and stator.
l I
C. high counter electromotive force at low rotor speeds.
j D. windage losses between the rotor and stator.
ANSWER: A.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
32 TOPIC:
191006 KNOWLEDGE: ' K l.07 QID:
P1934 (Rev)
Refer to the drawing of a lube oil heat exchanger (see figure below).
Given the following information, which one of the following is the temperature of the cooling water exiting the heat exchanger (T,,,,)?
i 4
s
= 1.5 x 10 lbm/hr ou 4
s,m,
= 2.5 x 10 lbm/hr C
= 1.1 Btu /lbm-F rou C,,,,, = 1.0 Btu /lbm "F 7
T,.i,
= 92 F T,,,,
=7 T n.i,
= 160*F o
T a.,
= 110 F o
A. Il0*F B. I15*F C. 120*F D. 125
- F ANSWER: D.
Il"'";*,t. y"idl7!Ul!$@'~U'T"lano
~
$. ' gsem*=ww o
nunnne wAren m.
4, i ~ ~u E1 Pim L
E
-N PflEI b!i!!E(Nih) l LUDE OIL LUBE OIL HEAT EXCHANGER i
USNRC GENERIC FUNDAMENTALS EXAMINATION
[
APRIL 1999 PWR - FORM A PROOF: m,c,,AT, = m,c AT, g
I o Po o = T""' * - T'" "
m,c,,
T*
P T
= T.
+
out w in w 4
= 92 + 1.5 x 10 x 1.1 x 50 4
- 2.5 x 10 x 1.0
= 92+33
= 125'F QUESTION:
33 TOPIC:
191006 KNOWLEDGE: Kl.08 QID:
Pl732 (B1732)
Which one of the following will reduce the rate of heat transfer between two liquids in a heat exchanger? (Assume single-phase conditions and a constant specific heat for both liquids.)
A. The inlet temperatures of both liquids are decreased by 20*F.
B. The inlet temperatures of both liquids are increased by 20 F.
C. The inlet temperature of the hotter liquid is increased by 20*F.
D. The inlet temperature of the colder liquid is increased by 20 F.
ANSWER: D. -
I USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A I~
l
- QUESTION:
34 TOPIC:
191006
. KNOWLEDGE: K1.14 QID:
NEW Which one of the following explains why the introduction of a significant amount of air into an operating main condenser will reduce the vacuum in the condenser?
A. A layer of air will form inside the condenser shell, reducing heat transfer from the turbine exhaust steam to the condenser shell.
B. Air molecules will become entrained in the turbine exhaust steam, reducing heat transfer through the condenser tubes.
C. Air ejectors will become air bound and lose their ability to remove main condenser gases.
D. A steam-air mixture will develop in the condenser, which requires a higher condenser pressure for condensation to occur.
ANSWER: B.
QUESTION:
35 TOPIC:
191007 KNOWLEDGE: Kl.01 QlD:
P2035 (B2039)
Which one of the following conditions will lead to channeling in a demineralizer?
A. Suspended solids and insoluble particles forming a mat on the surface of the resin bed B. A sudden 30'F decrease in the temperature of the influent to the demineralizer C. Exhaustion of the resin bed due to high conductivity of the demineralizer influent D. Operation of the demineralizer with influent flow rate at 10% below design flow rate ANSWER: A.
t 1
1 i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
36 DELETED I
QUESTION: 37 TOPIC:
191007 KNOWLEDGE:
Kl.14 QlD: P337 The plant is operating at 70% steady state power level when the temperature of reactor coolant letdown passing through a boron-saturated mixed bed ion exchanger is decreased by 20 F.
As a result, the boron concentration in the effluent of the ion exchanger will because the affinity of the ion exchanger for boron atoms has A. decrease; increased B. decrease; decreased C. increase; increased D. increase: decreased ANSWER: A.
[i USNRC GENERIC FUNDAMENTALS EXAMINATION I
APRIL 1999 PWR - FORM A l'
QUESTION:
38 TOPIC:
191008 KNOWLEDGE: K1.02
.QlD:
P739 (B241)
- Which onc of the following available local circuit breaker indications will provide the most reliable and positive indication that a bus feeder breaker is open? (Assume the following indications and mechanisms are operating properly.)
A. Load-side ammeter and overcurrent trip flags B. Load-side ammeter and load-side voltage C. OPEN/ CLOSED mechanical flag indication and load-side voltage D. OPEN/ CLOSED mechanical flag indication and overcurrent trip flags ANSWER: C.
l
- L
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
39 TOPIC:
191008 KNOWLEDGE: Kl.06 QlD:
P2239 (Rev)
Refer to the drawing of a valve motor control circuit (see figure below) for a valve that is currently fully open and has a 10 second stroke time. Limit switch LS2 has failed open. (Note:
"LS" contacts are not necessarily shown in their current condition.)
Which one of the following describes the valve response if the control switch is taken to the "Close" position for 2 seconds and then released?
A. The valve will not move.
B. The valve will close fully.
C. The valve will begin to close and then stop moving.
D. The valve will begin to close and then open fully.
ANSWER: A.
+125 VDC Neutral Neutral
% sa i
% am >
O O
O O
O O
~IS"~""DM~n" Close C
(R)
(G)
K12_ _ Open Alarm T
_1s1
_LS2 JS3
_JM
_1S5
~~
~~
~~
~
Open When Open When Open whe Open Whes Open When Yalve Fouy Opes Valve Fauy Closed Valve Funy Valve FuBy Valve Fauy K2-1 Kl.1 Open M
Open El K2 Open Reisy Close Relay VALVE MOTOR CONTROL CIRCUIT l '
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
40 TOPIC:
191008 KNOWLEDGE: Kl.04 QID:
P2041 (Rev) '
Two identical 1000 MW electrical generators are operating in parallel supplying the same isolated electrical bus. The generator output breakers also provide identical protection for the generators. Generator A and B output indications are as follows:
Generator A Generator B 22 KV 22 KV 60.2 Hertz 60.2 Hertz 200 MW 200 M W.
A malfunction causes the voltage regulator setpoint for generator A to slowly increase continuously toward a maximum of 25 KV. If no operator action is taken, generator B output current will:
A. initially decrease, and then increase until the output breaker for generator A trips on overcurrent.
B. initially decrease, and then increase until the output breaker for generator B trips on overcurrent.
C. increase continuously until the output breaker for generator A trips on overcurrent.
D. increase continuously until the output breaker for generator B trips on overcurrent.
ANSWER: A. l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
41 TOPIC:
191008 KNOWLEDGE: Kl.08 I
QID:
P341 (B343)
The main generator is being paralleled to the grid. Generator voltage has been properly adjusted and the synchroscope is rotating slowly in the clockwise direction. The generator breaker mitst be closed just prior to the synchroscope pointer reaching the 12 o' clock position to prevent:
A. motoring of the generator due to unequal frequencies.
B. excessive arcing within the generator output breaker due to out-of-phase voltages.
C. excessive MW load transfer to the generator due to unequal frequencies.
D. excessive MVAR load transfer to the generator due to out-of-phase voltages.
I ANSWER: B.
QUESTION:
42 l
TOPIC:
191008 l
KNOWLEDGE: Kl.08 QID:
- P2044 (B2043)
Two identical 1000 MW electrical generators are being connected to the same isolated electrical bus, Generator A is currently supplying the bus. Generator A and B output indications are as follows:
Generator A Generator B 4160 Volts 4140 Volts l
60.2 Hertz 60.8 Hertz 25 M W 0MW 10 MVAR 0MVAR l
i When the output breaker for generator B is closed, which generator is more likely to trip on reverse power?
A. Generator A due to the higher initial voltage B. Generator A due to the lower initial frequency C. Generator B due to the lower initial voltage l
D. Generator B due to the higher initial frequency ANSWER: B. l
1 USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
43 TOPIC:
191008 KNOWLEDGE: Kl.10 QID:
P943 (B2244)
What is an advantage of using high voltage electrical disconnects instead of circuit breakers to isolate main power transformers?
A. Disconnects provide positive visual indication that the circuit is broken.
B. Disconnects can be operated either locally or remotely.
C. Disconnects are cheaper and provide the same automatic protection as a breaker.
D. Disconnects are capable ofisolating all transformer output phases.
ANSWER: A.
QUESTION:
44 TOPIC:
191008 KNOWLEDGE: Kl.ll QID:
P1044 The following indications are observed in the control room for a normally-open breaker that directly starts / stops a 480 Vac motor:
Red position indicating light is on.
Green position indicating light is off.
Load current indicates 0 amps.
Supply voltage indicates 480 volts.
What is the condition of the breaker?
A. Open and racked in B. Closed and racked in C. Open and racked to " test" position D. Closed and racked to " test" position ANSWER: D. 1
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
45 TOPIC:
192001 KNOWLEDGE: Kl.02 QID:
P2145 (Rev)
When comparing a delayed neutron to a prompt neutron born from the same fission event, the prompt neutron is more likely to:
A. leak out of the core while slowing down.
B. be captured by a U-238 nucleus at a resonant energy.
C. be captured by a Xe-135 nucleus.
D. cause thermal fission of a U-235 nucleus.
ANSWER: A.
QUESTION:
46 TOPIC:
192002 KNOWLEDGE: Kl.10 QID:
P345 (Rev)
A plant is operating at 100% power with rod control in Manual. If no operator action is taken, then during the next two weeks of steady-state operation at 100% power shutdown margin will:
A. continuously decrease B. initially decrease, then return to the same value due to changing coolant temperature.
C. continuously increase D. initially increase, then return to the same value due to changing coolant temperature.
ANSWER: C. :
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
47 TOPIC:
192002 KNOWLEDGE: Kl.13 QlD:
P1647 (Rev)
A plant malfunction requires a rapid reactor power decrease from 100% to 90%. The crew hurriedly performs the downpower transient using control rod insertion when necessary. Reactor coolant boron concentration is not changed.
If the initial shutdown margin was 3.500% AK/K, which one of the following describes the shutdown margin at the lower power level? (Neglect any changes in core fission product reactivity.)
. A. Less than 3.500% AK/K due only to the power defect.
B. Less than 3.500% AK/K due only to the insertion of control rods.
C. Less than 3.500% AK/K due to the combined effects of control rod insertion and power defect.
D. Equal to 3.500% AK/K regardless of the reactivity effects of control rod insertion and power defect.
ANSWER: D.
PROOF:
Variations in power and/or control rod position do n_ol affect operating shutdown margin unless RCS boron concentration is also changed. L
F l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR FORM A QUESTION:
48 TOPIC:
192003 KNOWLEDGE: Kl.07
-QID:
P1548 (B1250)
Two reactors are identical in every way except that reactor A is at the end of core life and reactor B is at the beginning of core life. Both reactors are critical at 104o power.
If the same amount of positive reactivity is added to each reactor at the same time, the point of adding heat will be reached first by reactor because it has a delayed neutron fraction.
A. A; smaller B. A; larger C. B; smaller D. B; larger ANSWER: A.
QUESTION:
49 TOPIC:
192003 KNOWLEDGE: Kl.08 QlD:
NEW A reactor was stable at 80% power when the reactor operator withdrew control rods continuously for 2 seconds. Which one of the following affects the amount of" prompt jump" increase in reactor power for the control rod withdrawal?
A. The duration of control rod withdrawal B. The differential control rod worth C. The total control rod worth D. The magnitude of the fuel temperature coefficient f
I ANSWER: B.
I i l
((
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
50 l
TOPIC:
192004 l
KNOWLEDGE: K1.03/K1.06
_QID:
P2150 Which one of the following conditions will cause the moderator temperature coefficient (MTC) to become more negative? (Consider only the direct effect of the indicated change on MTC.)
A. The controlling bank of control rods is inserted 5% into the core.
B. Fuel temperature decreases from 1500 F to 1200 F.
C. Reactor coolant boron concentration increases by 20 ppm.
D. Moderator temperature decreases from 500 F to 450 F.
ANSWER: A.
QUESTION:
51 TOPIC:
192004 KNOWIIDGE: Kl.08 QlD:
P652 Which one of the following adds the most positive reactivity following a trip / scram from full power at the beginning of core life? (Assume reactor coolant system parameters stabilize at their normal post-trip values.)
A. Moderator temperature coefficient B. Void coefficient C. Pressure coefficient D. Dopplercoefficient ANSWER: D.
l' L
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A e
l QUESTION:
52 TOPIC:
192004
' KNOWLEDGE: Kl.10 l
QID:
P1252 l
l Differential boron worth (AK/K/ ppm) becomes more negative as:
A. burnable poisons deplete.
i B. boron concentration increases.
l C. moderator temperature increases.
D. fission product poison concentration increases.
ANSWER: A.
i
! L
7.-
USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1999 PWR - FORM A l
l QUESTION:
53 I
TOPIC:
192004 KNOWLEDGE: Kl.12 QID:
P2353 (Rev)
Given the following initial parameters:
Reactor power
= 100%
Total power coefficient
= -0.020% AK/K/%
Boron worth
= -0.010% AK/K/ ppm Rod worth
= -0.025% AK/K/ inch inserted Initial reactor coolant system (RCS) boron concentration
= 500 ppm i
Which one of the following is the final RCS boron concentration required to support decreasing plant power to 30% by boration/ dilution with 20 inches of inward control rod motion? (Assume no change in xenon reactivity.)
A. 410 ppm i
B. 425 ppm C. 575 ppm D. 590 ppm ANSWER: D.
PROOF:
AK/K from rods = 20" x (-0.025% AK/K/in) = -0.50% AK/K AK/K from P.D. = -70% x (-0.020% AK/K/%) = +1.4% AK/K Total AK/K = AK/K rods + AK/Kpo = -0.50% AK/K + 1.4% AK/K = +0.90%AK/K Boron reactivity needed to balance reactivity change from power and rods is
.-0.90%AK/K
-0.90% AK/K
-0.010% AK/K/ ppm = 90 ppm boron increase L
500 + 90 ppm = 590 ppm '
m USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
54.
TOPIC:
192005 KNOWLEDGE: Kl.05 i
QID:
P1755 (Rev)
A control rod is positioned in a reactor with the following neutron flux parameters:
Core average thermal neutron flux = 1.0 x 10i2 n/cm -sec 2
i2 2
Control rod 'ip thermal neutron flux = 4.0 x 10 n/cm -sec
-If the control rod is slightly inserted such that the control rod tip is located in a thermal neutron flux of 1.6 x 10" n/cm -sec, then the differential control rod worth will increase by a factor of 2
. (Assume the core average thermal neutron flux is constant.)
A. 2 1
B. 4 C. 8 D. 16 ANSWER: D.
PROOF:
CRW=
1 9sa CRW (9:ip/9iipi)*
2
- CRW, (9,,j9,g)2 CRW, (1.6 x 10'3/4 x 10 )2 i2 2
CRW (1 x 10: /1 x 10' )2 2
l CRW,3 2
CRW I
2 CRW = CRW,(16) 2 i-1 USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A L
QUESTION:
55 i
TOPIC:
192005 j
l
. KNOWLEDGE: Kl.10 QID:
P455 Which one of the following describes why most of the power is produced in the lower half of a j
core that has been operating at 100% power for several weeks with all control rods withdrawn at the beginning of core life?
A. Xenon concentration is lower in the lower half of the core.
i B. The moderator to fuel iatio is lower in the lower half of the core.
C. The fuel loading in the lower half of the core contains a higher U-235 enrichment.
D. The moderator temperature coefficient of reactivity is adding less negative reactivity in the lower half of the core.
ANSWER: D.
QUESTION:
56 TOPIC:
192005 KNOWLEDGE: Kl.16 QID:
P557 (Rev)
A reactor has been operating at 80% power for four weeks with the controlling rod group inserted 15% from the fully withdrawn position.
Which one of the following will be significantly affected by withdrawing the controlling rod group an additional 5%? (Assume reactor power does not change.)
A. Total xenon reactivity B. Axial power distributien C. Radialpowerdistribution D. Quadrant (azimuthal) power distribution ANSWER: B.
e USNRC GENERIC FUNDAMENTALS EXAMINATION 4
APRIL 1999 PWR - FORM A QUESTION:
57' TOPIC:
192005 KNOWLEDGE: Kl.16
'QID:
P1457 A reactor is operating at 75% power. Assuming reactor power does not change, which one of the following compares the effects of dropping a center control rod to the effects of partially inserting (50%) the same control rod?
j A. A dropped rod causes a greater change in shutdown margin.
. B. A dropped rod causes a smaller change in shutdown margin.
C. A dropped rod causes a greater change in axial power distribution.
D. A dropped rod causes a greater change in radial power distribution.
ANSWER: D.
i QUESTION:
58 TOPIC:
192006 KNOWLEDGE: Kl.03 QID:
NEW i
Reactors A and B are operating at steady-state 100% power with equilibrium core Xe-135. The reactors are identical except that reactor A is operating at end of core life and reactor B is operating at beginning of core life.
Which reactor has the greatest core Xe-135 concentration?
l A. Reactor A due to the smaller 100% power thermal neutron flux B. Reactor A due to the greater 100% power thermal neutron flux l
C. Reactor B due to the greater 100% power thermal neutron flux D. Reactor B due to the smaller 100% power thermal neutron flux ANSWER: D.
r?
L I
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A I
~ QUESTION:.
59 TOPIC:
192006 KNOWLEDGE: Kl.06 QID:
P2060 (Rev)
A reactor is initially operating at 100% power with equilibrium core xenon-135. Power is decreased to 50% over a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period and average reactor coolant temperature is adjusted to 572 F using manual rod control. Rod control is left in Manual and no subsequent operator i
actions are taken.
Considering only the reactivity effects of core xenon-135 changes, which one of the following describes the average reactor coolant temperature 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after the power change is completed?
A. Greater than 572*F and decreasing slowly B. Greater than 572*F and increasing slowly C. Less than 572*F and decreasing slowly.
D. Less than 572't: and increasing slowly ANSWER: D.
QUESTION:
60 TOPIC:
192006 KNOWLEDGE: Kl.07 QID:
P1358 (B1361)
A reactor has been operating at _75% power for two months. A manual reactor trip is required for a test. The trip will be followed immediately by a reactor startup with criticality scheduled to occur 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the trip.
The greatest assurance that xenon reactivity will permit criticality during the startup will be attained if the reactor is operated at power for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the trip and if criticality is rescheduled for hours after the trip.
A.100%; 8 B. 100%; 16 l
C. 50%; 8 D. 50%; 16 ANSWER: D.
USNRC GENERIC FUNDAMENTALS EXAMINATION
' APRIL 1999 PWR - FORM A QUESTION:
~61-TOPIC:
192006 KNOWLEDGE: Kl.09 i
.QID:
P2260 (Rev)
A reactor is initially shut down with no xenon in the core. A reactor startup is performed and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later power level is at 25%. The shift supervisor has directed that reactor power and reactor coolant temperature be maintained constant at this level for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
To accomplish this, control rods will have to be:
i A. withdrawn periodically for the duration of the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
]
B. inserted periodically for the duration of the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
C. withdrawn periodically for 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, then inserted periodically, i
D.' inserted periodically for 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, then withdrawn periodically.
ANSWER: A.
i QUESTION:
62 TOPIC:
192006 KNOWLEDGE: Kl.01 QID:
P2158 A fission product poison can be differentiated from all other fission products in that a fission product poison:
A. will be radioactive fer thousands of years.
B. is produced in a relatively large percentage of thermal fissions.
C. has a relatively high probability of absorbing a fission neutron.
D. is formed as a gas and is contained within the fuel pellets and fuel rods.
ANSWER: C.
l I
p l
t
(
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A k
' QUESTION:
63 TOPIC:
192006 KNOWLEDGE: Kl.14 QID:
P563 A reactor is operating at 100% power at the beginning of core life with equilibrium core xenon-135. Reactor power is reduced, within a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period, to 50% by boration only. Control rods are maintained fully withdrawn. The following parameter values are given:
PRIOR TO AFTER POWER CHANGE POWER CHANGE Reactor power:
100 %
50%
Reactor coolant system boron concentration:
740 ppm 820 ppm Control rod position:
Fully Fully Withdrawn Withdrawn What is the effect on power distribution in the core during the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following the power reduction?
'A. Power production in the top of the core increases relative to the bottom of the core.
B. Power production in the top of the core decreases relative to the bottom of the core.
C. There is no relative change in power distribution in the core.
D. It is impossible to determine without additional information.
l ANSWER: A.
l l
t 44
m USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
64 DELETED l
l
}
QUESTION:
65 TOPIC:
192008 KNOWLEDGE: K1.04 QID:
P1972 (B1067)
At one point during a reactor plant startup and approach to criticality, count rate is noted to be 780 cps, and K,g is calculated to be 0.92. Later in the same startup, stable count rate is 4160 cps.
What is the new K,u?
A. 0.945 B. 0.950 3
C. 0.975 j
l D. 0.985 I
ANSWER: D.
l PROOF:
CR, 1-k 2 CR 1 - k, 2
l CR, (1 -k ) CR
= 1 -k 1
8 2
80 '
(1 -0.92) 1-k
=
2
- 4160, t
0.015 = 1 -k2 1
i k = 0.985 2
- i 1
I
E 1
j V
USNRC GENERIC FUNDAMENTALS EXAMINATION
' APRIL 1999 PWR - FORM A QUESTION:
66 TOPIC:
192008 KNOWLEDGE: Kl.06 QlD:
P466 During a reactor startup as K,y increases toward 1.0, the value of 1/M:
A.
decreases toward zero.
B.
decreases toward 1.0.
C.
increases toward infinity.
D.
increases toward 1.0.
4 ANSWER: A.
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A
- QUESTION:
67 TOPIC:
192008 KNOWLEDGE: Kl.07 QlD:
P1266 A reactor is subcritical with a startup in progress. Which one of the following conditions will result in a critical rod position that is lower than the estimated critical rod position?
A. A malfunction resulting in control rod speed being faster than normal speed l
B. A malfunction resulting in control rod speed being slower than normal speed C. Delaying the time of startup from 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> following a trip from 100% power equilibrium conditions
)
D. Inadvertent dilution of reactor coolant system boron concentration l
{
ANSWER: D.
l QUESTION:
68 TOPIC:
192008 i
KNOWLEDGE: Kl.14 l
QlD:
P2269 (Rev) i A reactor is currently at 10~3% power with a positive 60 second reactor period. An amount of j
necative reactivity is added to the core that places the reactor on a negative 40 second reactor period.
If the same amount of positive reactivity is added to the core approximately 5 minutes later, l
reactor power will:
l A. increase and stabilize at the point of adding heat.
i l
B. increase and stabilize at 10-3%.
l C. continue to decrease on a negative 40 second period until the equilibrium source neutron level is reached.
D. continue to decrease with an unknown period until the equilibrium source neutron level is l
reached.
l-1 ANSWER: A.
i l
p USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
69 TOPIC:
192008 KNOWLEDGE: Kl.17 QID:
P2069 (B2072)
With a reactor on a constant period of 180 seconds, which one of the following power changes requires the longest amount of time to occur?
A. 3% power to 5% power B, 5% power to 15% power C. 15% power to 30% power D. 30% power to 60% power ANSWER: B.
PROOF:
P, = P e*
o tin P/P, = t (in 5/3)(180) = 0.51(180) = t = 91.8 seconds (In 15/5)(180) = 1.l(180) = t = 198 seconds (in 30/15)(l80) = 0.693(180) = t = 124.8 seconds (In 60/30)(l80) = 0.693(l80) = t = 124.8 seconds 1
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
70 TOPIC:
192008 KNOWLEDGE: Kl.22 QlD:
NEW During a core refueling, fuel assemblies with higher enrichments of U-235 were ir. stalled to prolong the fuel cycle from 12 months to 16 months. What is a possible consequence of offsetting all the excess positive reactivity of the new fuel with a higher concentration of boron in the reactor coolant?
A. Boron will precipitate out of the reactor coolant during a cooldown.
B. An RCS temperature decrease will result in a negative reactivity addition.
C. Power changes requiring dilution of RCS boron will take longer.
D. The differential boron worth will become positive.
ANSWER: B.
QUESTION:
71 TOPIC:
192008 KNOWLEDGE: Kl.23 QL);
P1965 (B1369)
Shortly after a reactor trip, when reactor power indicates 10 3%, a stable negative period is attained. Reactor power will decrease to 10 % in approximately seconds.
d A. 380 B. 280 C. 180 D. 80 ANSWER: C.
PROOF:
A power decrease of I decade at -1/3 dpm takes 3 minutes. I
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
72 l
TOPIC:
192008 KNOWLEDGE: Kl.27 QlD:
P1372 (Rev)
A reactor had been operating at 100% power for six months when a steam line rupture occurred that resulted in a reactor trip and all steam generators (S/Gs) blowing down (emptying) after approximately I hour. The S/G blowdown caused reactor coolant system (RCS) temperature to decrease to 400*F.
Given the following information, what was be the average RCS heatup rate during the 5 minutes immediately after all S/Gs became empty?
Reactor rated thermal power:
2400 MWt Decay heat:
1.0% rated thermal power Reactor coolant pumps heat input to the RCS:
13 MWt RCS total heat loss:
2.4 MWt RCSc:
1.1 Btu /lbm-F p
RCS inventory (less pressurizer):
325,000 lbm l
A. '8 to 15 F/ hour B. 25 to 50*F/ hour C, 80 to 150 F/ hour l
D. 300 to 400*F/ hour i
ANSWER: D.
PROOF:
Net RCS heat addition Decay heat input + RCP heat input - RCS heat loss
=
6
[2400 MWt (1.0%) + 13 MWt - 2.4 MWt] (3.41 x 10
=
Btu /hr/MWt) 8 1.1 x 10 Btu /hr
=
lieatup Rate Net RCS heat addition + RCS mass + RCS cp
=
8 1.1 x 10 + 325,000 + 1.1
=
307 F/hr
=
I i ;
O l
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A
' QUESTION:
73
' TOPIC:
193003 KNOWLEDGE: K1.14-QlD:
P2074 (B2074)
Consider a saturated water / steam mixture at 500*F with a quality of 90% If the pressure of the mixture is decreased with no heat gain or loss, the temperature of the mixture will and the quality of the mixture will
. (Assume'the mixture remains saturated.)
- A. decrease; decrease B. decrease; increase -
l C. remain the same; decrease D. remain the same; increase j
ANSWER: B.
4 QUESTION:
74 I
TOPIC:
193001 l
KNOWLEDGE: Kl.03 l
QID:
P2373 (Rev) i 1
1 i
Refer to the drawing of four identical tank differential pressure level detectors (see figure on next page).
i The tanks are identical and they are presently at 2 psig overpressure,60*F, and the same constant water level. They are located within a sealed containment structure that is being maintained at atmospheric pressure. All level detectors have been calibrated and are producing the same level l
indication. A ventilation malfunction causes containment structure pressure to decrease to 13 1
psia.
Which level detectors will produce the highest indication?
A. I and 2 B. 3 and 4 1
C. I and 4 D. 2 and 3 '
l ANSWER: D. i k1
USNRC GENERIC FUNDAMENTAL S EXAMINATION APRIL 1999 PWR - FORM A REFERENCE LEG FILL CONNECTION GAS OR VAPOR PRESSURE h
c
/ AA
/
i-/
/
DIP DIP DETECTOR DETECTOR NO.1 NO. 2 l
l CEFERENCE LEO FILL CONNECTION O
GAS OR VAPOR
-I-PRESSURE p
[
WATER
/
/
DIP DIP DETECTOR DETECTOR NO. 3 NO. 4 TANK DIFFERENTIAL PRESSURE LEVEL DETECTORS USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
75 TOPIC:
193003 KNOWLEDGE: Kl.25 QID:
' P2375 (Rev) i Which one of the following is the approximate amount of heat required to convert 2.0 lbm of
{
water at 100*F and 100 psia to a superheated vapor at 400 F and 100 psia?
]
A. Ii19 Btu i
B. Il59 Btu i
C. 2238 Btu D. 2318 Btu ANSWER: D.
PROOF:
Enthalpy of water at 100*Fi 100 psia is 68.0 Btu /lbm -
Enthalpy of superheated vapor at 100 psia and 400 F is 1227.4 Blu/lbm Enthalpy of saturated vapor at 100 psia is 1187.2 Btu /lbm l
Enthalpy of saturated water at 100 psia is 298.5 Btu /lbm l
X = 2 lbm (1227.4 Btu /lbm - 68 Btu /lbm)
X = 2(1159.4) Btu l
X = 2318.8 Btu i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
76 TOPIC:
193004 KNOWLEDGE: K1.11 QID:
P1176 (Rev)
A plant is operating at 80% power with 5*F of condensate depression in the main condenser. If the condensate depression decreases to 2*F, plant efficiency will and the probability of condensate pump cavitation will A. increase; increase
_ B. increase; decrease C. decre.se; increase D. decreaw; decrese ANSWER: A.'
QUESTION:
77 TOPIC:
193004 KNOWLEDGE: Kl.15
'QID:
P1677 A reactor plant is being maintained at 2,220 psig with a pressurizer temperature of 652 F. A pressurizer safety / relief valve is leaking to a collection tank which is being held at 20 psig.
l Neglecting heat losses to ambient, which one of the following is the approximate temperature of j
the fluid downstream of the relief valve?
A. 162*F l
B. 228 F i
C. 259*F D. 320 F ANSWER: C.
PROOF:
PRT pressure = 20 psig + 15 psi = 35 psia Saturation temperature at 35 psia from Steam Tables is
- 259 F USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
78 I
DELETED i
F:l I
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
79 TOPIC:
193006 KNOWLEDGE: Kl.05 QlD:
Pl779 (B1783)
A 100 gpm leak has developed in a cooling water system that is operating at 45 psig. Which one of the following will be the approximate leak rate when system pressure has decreased to 30 psig?
A. 25 gpm B. 50 gpm C. 67 gpm D. 82 gpm ANSWERiD.
PROOF:
p,p
- b. b F
, /A P,
2 2
F = F, 2
rfi
= 100 A 5.48
= 100 6.71
= 100 (.817)
= 82gpm m
USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1999 PWR - FORM A QUESTION:
80 TOPIC:
193006 KNOWLEDGE: Kl.04 QID:
P2079 (B2081)
Which one of the following will minimize the possibility of water hammer?
A. Draining the discharge line of a centrifugal pump after shutdown B. Draining condensate out of steam lines before and after initiating flow C. Starting a centrifugal pump with its discharge valve fully open D. Starting a positive displacement pump with its discharge valve partially closed l
ANSWER: B.
i QUESTION:
81 TOPIC:
193006 KNOWLEDGE: Kl.06 QID:
P1480 (Rev) i Reactor coolant systen i9CS) hot leg temperature is 552*F and RCS pressure is decreasing due to a small leak. Which one of the following pressure ranges includes the pressure at which two-phase flow will first occur in the hot leg?
A. I100 to 1051 psig B. 1050 to 1001 psig C.1000 to 951 psig D. 950 to 901 psig ANSWER: B.
PROOF:
Psat for 552*F is 1062.6 psia, which equals 1047.9 psig. _ - -
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
82 TOPIC:
193006 KNOWLEDGE: Kl.15 QID:
P2481 (Rev)
Water at 90*F and 50 psig is flowing through a 10-inch diameter pipe at 100 lbm/sec. The pipe then splits into two pipes, a 6-inch diameter pipe and an 8-inch diameter pipe.
Disregarding any flow restrictions other than pipe size, which one of the following lists the approximate flow rates through the 6-inch and 8-inch diameter pipes? (Assume fluid velocity is the same in each pipe.)
6-inch Pipe 8-inch Pipe (lhm/sec)
(Ibm /sec)
A.
24 76 B.
32 68 C.
36 64 D.
40 60 ANSWER: C.
PROOF:
m = Av and y are the same for all conditions Therefore, m = A
/u m6 m,
= A /As, 6
m-
=(mus)(A )/A,
6 s
= 100 (9n )/(9a + 16n)
= 900/25
= 36 m /m,
= A,/A y, a s m,
=(mus)(A,)/As,
= 100 (16n )/(9n + 16x)
= 1600/25
= 64 - - - _ _ _ _ _ _ _ _
[.
USNRC GENERIC FUNDAMENTALS EXAMINATION h
APRIL 1999 PWR - FORM A i
QUESTION:
83 TOPIC:
193006 KNOWLEDGE: ~ K1.11 QlD:
P2181
. Refer to the drawing of a cooling water system in which only pump A is operating and the pump discharge valve is currently 50% open (see figure below).
Which one of the following will cause pump A to operate closer to the conditions that will cause cavitation?
A. Starting pump B B. Positioning the discharge valve to 40% open C. Raising the water level in the surge tank by 2 feet D. Increasing heat exchanger service water flow rate by 10%
ANSWER: A.
P fi"a' HEAT EXCHANGER HEA Y
LOADS 1r A R
$1'sA
'd-O l
PUMP A PUMPG i
4 I
COOLING WATER SYSTEM I I I
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
84 TOPIC:
193007 KNOWLEDGE: Kl.06 QID:
P384 (B386)
The power range nuclear instruments have been adjusted to 100% based on a calculated
- calorimetric (secondary heat balance). Which one of the following will result in actual reactor power being less than indicated reactor power?
A. The feedwater temperature used in the calorimetric calculation is higher than actual feedwater temperature.
B. The reactor coolant pump heat input term is omitted from the calorimetric calculation.
C. The feedwater flow rate used in the calorimetric calculation is lower than actual feedwater flow rate.
D. The steam pressure used in the calorimetric calculation is higher than actual steam pressure.
ANSWER: B.
4 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A
! QUESTION:
85 TcPIC:
193007 KNOWLEDGE: Kl.08 QlD:
F2085 (Rev)
During a plant outage,5% of all steam generator (S/G) tubes were plugged. Full-power reactor coolant system flow rate and average coolant temperature (T,,,) have not changed. Given the following 100% power conditions before the outage:
T.,, = 588.0*F Tsm = 542.0 F Which one of the following will be the approximate S/G pressure when the plant is returned to 100% power after the outage?
A. 998 psia B. 979 psia C. 961 psia D. 944 psia ANSWER: C.
PROOF:
UAAt (before) = UAAt (after)
If A decreases by 5%, then At must increase by 5%. If Twt s constant, then i
Tsy must decrease by 5% of At (46*F) or 2.3 *F.
542.0 - 2.3 = 539.7 *F Psat for 539.7*F is approx. 961 psia _
L USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A
. QUESTION:
86 TOPIC:
193008 KNOWLEDGE: Kl.02 QID:
P146 As compared to saturated nucleate boiling (bulk boiling), subcooled nucleate boiling:
A. occurs to a greater extent in the pressurizer and steam generators.
B. requires fewer Btu /lbm to convert reactor coolant to steam at a given temperature.
C, occurs less in the reactor core during normal plant operation.
D.. results in a lower convective heat transfer coefficient.
ANSWER: D.
QUESTION:
87 TOPIC:
193008 KNOWLEDGE: Kl.05 QlD:
P2288 (Rev)
A plant is operating with the following initial conditions:
Reactor power is 55% in the middle of a fuel cycle.
Axial and radial power distributions are peaked in the center of the core.
Which one of the following will increase the steady-state departure from nucleate boiling ratio?
A. A reactor trip occurs and one control rod remains fully withdrawn from the core.
B. A pressurizer malfunction decreases reactor coolant system pressure by 20 psig.
C. The operator decreases reactor coolant boron concentration by 5 ppm with no rod motion.
D. Core Xe-135 depletes in proportion to the axial and radial power distribution with no rod 6
motion.
' ANSWER: A.
py.-,
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
88-TOPIC:
193008 4
KNOWLEDGE:.K l.07
-QID:
P2188 (Rev).
Refer to the drawing of a pool boiling curve (see figure below).
Which one of the following describes the conditions in a fuel channel that is experiencing region IV heat transfer?
A. Complete steam blanketing of the fuel rod surface B. Alternate wetting and drying of the fuel rod surface C. Saturated nucleate boiling D. Subcooled nucleate boiling ANSWER: A.
I ll lil' IV l
l i
l LOG I
HEAT FLUX LOGAT POOL BOILING CURVE USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
89 TOPIC:
193008 KNOWLEDGE: Kl.06 QID:
P1087 (B1888)
How does critical heat flux (CHF) vary with core height during normal full power operation of the reactor?
A. CHF increases from the bottom to the top of the core.
B. CHF decreases from the bottom to the core midplane, then increases from the midplane to the top of the core.
C. CHF decreases from the bottom to the top of the core.
D. CHF increases from the bottom to the core midplane, then decreases from the midplane to the j
top of the core.
ANSWER: C.
QUESTION:
90 TOPIC:
193008 KNOWLEDGE: Kl.10 QID:
NEW If a reactor is being operated with DNBR at its limit, which one of the following is indicated?
A. None of the fuel rods are experiencing critical heat flux.
B. A small fraction of the fuel rods may be experiencing critical heat flux.
C. All radioactive fission products are being contained within the reactor fuel.
D. All radioactive fission products are being contained within either the reactor fuel or the reactor vessel.
ANSWER: B.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
91 l
TOPIC:
193008 KNOWLEDGE: Kl.15 QlD:
P2090 (Rev)
Which one of the following is most likely to result in steam bubble formation in a reactor vessel head while maintaining a 60 F subcooling margin in the hottest RCS hot leg?
A. Performing a 25*F/Hr RCS cooldown on natural circulation B. Performing a 50*F/Hr RCS cooldown on natural circulation C. Performing a 25*F/Hr RCS heatup on forced circulation D. Performing a 50*F/Hr RCS heatup on forced circulation
- ANSWER: B.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
92 TOPIC:
193008 KNOWLEDGE: Kl.22 QID:
P1492
- A reactor is operating at 100% power when a loss of offsite power occurs resulting in a reactor trip and a loss of forced reactor coolant circulation. Reactor coolant system (RCS) hot leg temperature is greater than cold leg temperature and steam generator (S/G) levels are stable.
.(CETC = core exit thermocouples)
Which one of the following combinations of parameter trends, occurring 30 minutes after the trip, indicates that natural circulation is occurring?
S/G
-RCS CETC p fPERATURE TEMPERATURE PRESSURES SUBCOOLING A.
Decreasing Stable Stable Increasing B.
Increasing Decreasing Increasing Decreasing C.
Decreasing Decreasing Decreasing Decreasing D.
Increasing Increasing Decreasing Increasing ANSWER: A.
QUESTION:
93 TOPIC:
193008 KNOWLEDGE: Kl.25 QID:
P793
. A reactor coolant system natural circulation cooldown is in propress via the steam generator (S/G) atmospheric steam relief valves (operated in manual correol). If high point voiding interrupts natural circulation, which one of the following will$ccur? (Assume feed flow rate, relief valve position, and decay heat level are constant.)
- e A. S/G level decreases and core exit thermocouple (CETC)h mperature indication increases.
B. S/G level decreases and CETC temperature indication dereases.
C. S/G level incr:ases and CETC temperature indication ihereases.
D. S/G level increases and CETC temperature indication heereases.
ANSWER: C.
{
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 M. F9RM A V
QUESTION:
94 TOPIC:
193009 KNOWLEDGE: Kl.07 QID:
P2094 (Rev)
A reactor is operating at steady state 80% reactor power with core power distribution peaked both radially and axially in the center of the core. Reactor coolant boron concentration changes are used to maintain a constant T and control rod position does not change.
m Neglecting any change in reactor poisons, during the next three months the maximum radial peaking factor will and the maximum axial peaking factor will A. increase; decrease B. increase; increase C. decrease; decrease D. decrease; increase ANSWER: C.
QUESTION:
95 TOPIC:
193009 KNOWLEDGE: Kl.05 QID:
NEW The linear power density thermal iiait is designed to prevent excessive temperatures during normal reactor plant operation; the limit is dependent upon the axial and radial peaking factors, of which, the peaking factor is the most limiting.
A. fuel clad; axial B. fuel clad; radial C. fuel pellet; axial --
D. fuel pellet; radial ANSWER: D.
t '
y l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
96 l
TOPIC:
193010 KNOWLEDGE: Kl.01 QlD:
P1696 Which one of the following increases the probability of brittle fracture of a reactor pressure vessel wall?
A. Performing a 50*F/hr cooldown at 1600 psia rather than a 50*F/hr cooldown at 1200 psia B. - A compressive stress rather than a tensile stress across the vessel wall C. A high reactor coolant temperature rather than a low reactor coolant temperature D. Changing wall design to increase toughness while maintaining the same strength ANSWER: A.
QUESTION:
97 TOPIC:
193010 KNOWLEDGE: Kl.02 QID:
P597 The nil-ductility transition temperature of the reactor vessel (RV) is the temperature:
A. below which the RV metal will elastically deform as reactor coolant system (RCS) pressure decreases.
B. below which the RV metal loses its ability to elastically deform as RCS pressure increases.
I C. above which the RV metal loses its ability to deform with ductility as RCS pressure increases.
D. ' above which the RV metal will elastically deform as RCS pressure decreases.
ANSWER: B.
f
) ~
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1999 PWR - FORM A QUESTION:
98 TOPIC:
193010 KNOWLEDGE: Kl.04' QID:
P399 (B399) i St ess on the reactor vessel inner wall is greater during cooldown than heatup because:
A. heatup stress totally offsets pressure stress at the inner wall.
B. both pressure stress and cooldown stress are tensile at the inner wall.
C. cooldown stress and heatup stress are both tensile at the inner wall, but cooldown stress is greater in magnitude.
D. the tensile cooldown stress at the inner wall is greater in magnitude than the compressive j
pressure stress at the same location.
ANSWER: B.
QUESTION:
99 TOPIC:
193010 KNOWLEDGE: Kl.05 QID:
P2298 (Rev)
Two identical reactors are currently shut down for refueling. Reactor A has an average lifetime power capacity of 60% and has been operating for 15 years. Reactor B has an average lifetime power capacity of 75% and has been operating for 12 years.
Which reactor, if any, will have the lowest reactor vessel nil ductility transition temperature?
A. Reactor A due to the lower average power capacity B. Reactor B due to the higher average power capacity C. Both reactors will have approximately the same nil ductility transition temperature because each core has produced approximately the same number of fissions.
D. Both reactors will have approximately the same nil ductility transition temperature because fast neutron irradiation from a shut down core is not significant.
ANSWER: C..
I!'
l i
USNRC GENERIC FUNDAMENTALS EXAMINATION L
APRIL 1999 PWR - FORM A
_ QUESTION:
100 TOPIC:
193010 KNOWLEDGE: Kl.06 QlD:
P99 A plant is shut down with the reactor coolant system at 1200 psia and 350*F. Which one of the following would be most likely to cause pressurized thermal shock of the reactor vessel?
A. A rapid depressurization followed by a rapid heatup j
B. A rapid depressurization followed by a rapid cooldown C. A rapid cooldown followed by a rapid pressurization D. A rapid heatup followed by a rapid pressurization i
ANSWER: C. _