ML20217L921
| ML20217L921 | |
| Person / Time | |
|---|---|
| Issue date: | 05/01/1998 |
| From: | Debra Mccain NRC (Affiliation Not Assigned) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9805040361 | |
| Download: ML20217L921 (150) | |
Text
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g UNITED STATES l..
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2006H001 l
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May 1,1998 i
NOTE TO:
Document Control Desk i
FROM:
Debbie McCain, Licensing Assi a
{
Division of Reactor Controls and Human Factors Operating Licensing Branch
SUBJECT:
APRIL 1998 GENERIC FUNDAMENTALS EXAMINATION (GFE)
Enclosed please find the April,1998 GFE examination and answer key to be placed in the PDR. if you have any questions I can be contacted at 415-1065.
Enclosure:
j As stated 1
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2' sg 9805040361 980501 PDR ORG NRRA j
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UNITED STATES NUCLEAR REGULATORY COMMISSION BOILING WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION APRIL 1998-FORM A l
Please Print Name:
Facility:
Docket No.:
Start Time:
Stop Time:
1 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 will be collected 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> after the examination stants. 'Illis examination applies to a typical boiling water reactor (BWR) 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.
j Applicant's Signature ;
?
RUIRE AND GUIDELINES FOR THE GENERIC FUNDAMENTAIR EXAMINATION
' During the administration of this examination the following rules apply:
l 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.
' Fillin the name ofyour facility.
3.
Fill in your individual docket number.
l 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 could also result in severe penalties.
9.
Restroom trips are limited. Only.0EE 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.
- 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.-
- 11. Tum in your examination materials, answer sheet on top, followed by the examination booklet, then p
exammation aids - steam table booklets, handouts and scrap paper used during the examination.
12.
After turning in your examination materials, leave the examination area, as defined by the proctor.
If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeited.
I
)
GENERIC FUNDAMENTALS EXAMINATION EOUATIONS AND CONVERSIONS HANDOUT SHEEI EOUATIONS l
Q = mc AT P = P,10**
p Q=sAh P=Pe" o
l A = A,e*
Q = UAAT CRw = S/(1 - K,g)
Q - 6'ncue u
CR (1 - K m) = CR (1 - K n2) i e
2 e
AT " $wat cire 1/M = CR /CR i
x K,y = 1/(1 - p)
DRW = 9[,/9g 2
P "(K n-1)/K n F = PA e
e SUR = 26.06/t s=pAV
.-0-P Wp., = sAPu t=
Aca P E = IR e
li P = - + 1 + A,g Eff. = Net Work Out/ Energy In i
t v(P - P ) + (V * - 9:2) + g(z2 - Z ) = 0 2
i 2
i 2g, g,
.1,y = 0.1 seconds-3 2
g, = 32.2 lbm-ft/lbf-sec CONVERSIONS 6
1 Mw = 3.41 x 10 Btu /hr 1 Curie = 3.7 x 10 dps I 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
-3
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
1 l
TOPIC:
291001 KNOWLEDGE:
Kl.01 QlD:
B1701 (Rev) -
' A vertical safety valve has a compressed spring assembly that is applying 2500 lbf to the top of the valve disk in opposition to system pressure. System pressure is being exerted on the underside of the valve disk that is 5 inches in diameter.
Which one of the following is the approximate system pressure at which the safety valve will open?
(Neglect the effect of atmospheric pressure.)
A.
32 psi B.
127 psi i
C.
159 psi D.
500 psi j
ANSWER: B.
PROOF:
F = PA P = F/A P = 2500/3.14(2.5)2 P = 2500/19.63 P = 127.35 psi l
QUESTION:
2 TOPIC:
291001 KNOWLEDGE:
Kl.02 QID:
B1801 (P1504) l Which one of the following is a difference between a typical relief valve and a typical safety valve?
'A.
Relief valves are capable of being gagged whereas safety valves aremal.
B.
The blowdown of a relief valve is greater than the blowdown of a safety valve.
C.
The actuator closing spring on a relief valve is in a compressed state whereas the actuator closing spring on a safety valve acts in tension.
D.
A relief valve gradually opens as pressure increases above the setpoint pressure whereas a safety valve fully opens at the setpoint pressure.
ANSWER: D.
-4
l 1
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
3 TOPIC:
291001 I
KNOWLEDGE:
Kl.03 l
QID:
New A control valve is most likely to experience cavitation when the valve is almost fully
{
because of a relatively pressure drop across the valve seat.
A.
open;large B.
open; small 1
l C.
closed;large D.
closed; small ANSWER: C.
l
' QUESTION:
4 TOPIC:
291001 KNOWLEDGE:
Kl.08 QlD:
B2004 (P2003)
A surveillance test procedure is being performed on a typical Limitorque motor-operated valve (MOV) used in an emergency core cooling system (ECCS) application. The declutch lever has been operated and released and the valve is being manually / locally opened by a technician. The MOV breaker is closed as required by the surveillance test procedure. During operation of the valve handwheel an ECCS actuation signal is received that normally energizes the valve motor and closes the valve.
How will the valve be affected by the actuation signal?
A.
The handwheel will disengage and the valve will automatically close.
B.
The handwheel will disengage and the valve will remain in the current position.
C.
The handwheel will remain engaged and the valve will automatically close.
l.
D.
The handwheel will remain engaged and the technician can continue to open the valve.
l ANSWER: A.
I USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A l
l l
' QUESTION:
5 TOPIC:
291001 KNOWLEDGE:
Kl.12 QlD:
B905 (Rev)
When comparing globe valves to gate valves, globe valves:
A.
are less effective at throttling flow.
B.
are less effective as pressure regulating valves.
C.
produce a smaller pressure decrease when fully open.
i D.
require less force to open against large differential pressures.
ANSWER: D.
l.
l J
l i
QUESTION:
6 TOPIC:
291002 KNOWLEDGE:
Kl.01 l
QID:
B9 (Rev)
A venturi is used to measure flow rate in a cooling water system. As the water flows from the throat to the discharge of the venturi, water pressure will and volumetric flow rate will i
. (Assume water is incompressible.)
l A.
increase; remain the same B.
increase; increase l
C.
decrease; remain the same D.
- decrease; decrease ANSWER: A.
)
l l
I USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
7 TOPIC:
291002 KNOWLEDGE:
Kl.05 QID:
B1608 (Rev)
Refer to the drawing of a horizontal pipe elbow (top view) in an operating water system (see figure below).
i Three separate bellows differential pressure flow detectors are connected to taps A, B, C, and D as follows:
DETECTOR TAPS AD A and D BD B and D CD C and D Assuming zero head loss in this section of pipe, how will the detectors be affected if system flow rate remains the same while system pressure increases from 1000 psig to 1200 psig?
A.
All detectors will indicate higher flow.
B.
Only two detectors will indicate higher flow.
I C.
Only one detector will indicate higher flow.
D.
Detector indication will not change.
ANSWER: D.
l tti 1_ A i
8 C
'I 11 n.ow b
i h
PIPE ELBOW. TOP VIEW l
_ 7 -
I
USNRC GENERIC FUNDAMENTALS EXAMINATION
' APRIL 1998 BWR-FORM A QUESTION:
8 TOPIC:
291002
- KNOWLEDGE:
Kl.09 QID:
New Refer to the drawing of a reactor vessel differential pressure level detector (see figure below).
A reactar vessel cooldown has resulted in a decrease in reactor vessel pressure from 900 psia to 400 psia in one hour. Without density compensation of the level instrumentation, at the end of the cooldown, reactor vessel level indication would indicate than actuallevel because the denLhy of the water in the has changed significantly.
A.
higher; reference leg B.
higher; reactor vessel j
C.
lower; reference leg D.
lower; reactor vessel ANSWER: B.
REACTOR VESSEL CONDENSING CHAMBER m
STEAM, '
7 EQUALIZING VALVE WATER l77rl D/P DETECTOR REACTOR VESSEL DIFFERENTIAL PRESSURE LEVEL DETECTOR i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
9 TOPIC:
291002 KNOWLEDGE:
Kl.12 l
QID:
B1610 (P510)
]
Refer to the drawing of a bellows-type differential pressure (D/P) detector (see figure below).
This D/P detecter is being used to measure system pressure in an operating high-pressure coolant injection system when the bellows develops a leak. If system pressure does not change, indicated
, pressure will:
A.
decrease because the spring will expand more.
B.
increase because the spring will cxpand more.
C.
decrease because the high pressure will compress the spring more.
D.
increase because the high pressure will compress the spring more.
ANSWER:. A.
MOVEAsLE VrALL SEALING
(
]
sELLOws iM[d
= __
yw ELLOWS BELLOWS. TYPE DIFFERENTIAL PRESSURE DETECTOR I
{
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
10 TOPIC:
291002 KNOWLEDGE:
Kl.04 QlD:
B307 (Rev)
An orifice is being used in an operating cooling water system to measure flow rate. Which one of the following will cause the differential pressure sensed across the orifice to decrease?
A.
System pressure decreases.
B.
System flow rate decreases.
C.
Debris becomes lodged in the orifice.
D.
A leak develops in the low pressure sensing line.
ANSWER: B.
i l
i i
i
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l j
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A
. QUESTION:
11.
' TOPIC:
291002
- KNOWLEDGE:
Kl.16 QID:~
.B1712 (P1313)
Which one of the following devices is commonly used to provide mmote indication of valve position
- on an analog meter in units of" percent of full open"? -
A.
B.
Reed switch
- C.
Resistance temperature detector
' D.
Linear variable differential transformer ANSWER: D.
QUESTION:
12 TOPIC:
291002 KNOWLEDGE:
Kl.19
-QID:
B1214 (Rev)
A reactor scrammed due to a loss-of-coolant accident I hour ago. To verify adequate reactor vessel L
.- water level, the source range monitors (SRMs) were fully inserted into the core.
L If the SRMs are currently in a voided section of the core, how will the count rate change when the SRMs are withdrawn below core water level?
A.-
Decrease due to decreased neutron migration length.
B.
Decrease due to increased moderator neutron absorption.
C.
Increase due to decreased neutron leakage.
~D.
Increase due to increased fast fission.
i
. ANSWER: C. l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
13 TOPIC:
291002 KNOWLEDGE:
Kl.21
.QID:
B2114 (P1812) j A gas-filled radiation detector operating in the proportional region is exposed to a constant gamma radiation field. If the applied voltage is increased but maintained within the proportional region, the rate ofion collection will:
A.
stay approximately the same because all of the primary ions were already being collected at the lower voltage.
B.
stay approximately the same because the detector is operating at saturated conditions.-
C.
increase because fewer primary ions are recombining in the detector prior to reaching the electrodes.
D.
' increase because more secondary ionizations are occurring in the detector.
ANSWER: D.
QUESTION:
14 TOPIC:
291002 KNOWLEDGE:
Kl.23 QID:
B1714 (Pl713).
A Geiger-Mueller radiation detector is located in a radiation field consisting of beta, gamma, and fast neutron radiation. Assuming each type of radiation enters the detector gas chamber and ionizes the detector gas, which one of the following describes the resulting detector pulse sizes?
A.
Beta radiation will produce a larger pulse size than either gamma or fast neutron radiation.
B.
Gamma radiation will produce a larger pulse size than either beta or fast neutron radiation.
C.
. Fast neutron radiation will produce a larger pulse size than either beta or gamma radiation.
D.
Beta, gamma, and fast neutron radiation will produce pulse sizes that are equal in magnitude.
j L
ANSWER: D.
i i
i.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A
. QUESTION:
15.
L TOPIC:
291003 l
. KNOWLEDGE:
Kl.03 QID:
B1317(Rev)
The level in a drain collection tank is being controlled by an automatic level controller and is initially tt the controller set point. Flow rate into the tank increases, causing tank level to incranse. The
' increasing level causes the controller to throttle open a tank drain valve. After a few minutes, a new, steady-state tank level above the original level is established, with the drain flow rate equal to the supply flow rate.
The controllerin this system uses control.
~ A.
on-off B.
proportional C.
proportional plus integral D.
' proportional plus integral plus derivative i
ANSWER: B.
)
l t
s l'
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
16 TOPIC:
291003 KNOWLEDGE:
Kl.04 QID:
B2017 (P2019) l Refer to the drawing of a pump with recirculation line (see figure below).
Which one of the following describes the response of the pump if a complete flow blockage occurs l
in the discharge line just downstream of the flow detector?
A.
The pump will overheat after a relatively short period of time due to a loss of both main flow and recirculation flow.
l B.
The pump will overheat after a relatively long period of time due to a loss ofmain flow only.
C.
The pump will overheat after a relatively long period of time due to a loss of recirculation flow only.
D.
The pump will be able to operate under these conditions indefinitely due to sustained main flow.
ANSWER: B.
j l
1 i
A h
ORIFICE VALVE
~}
Q
- DISCHARGE f-
=
SUCDON PUMP PUMP WITH RECIRCULATION LINE i
4 USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
17 TOPIC: '
291003
. KNOWLEDGE:
K'l.06 QlD:
B1916 (Rev)
Given the following diesel generator design ratings:
Overspeed trip setpoint:
2000 rpm Operating speed, no load:
1800 rpm Operating speed, fullload:
1720 rpm Which one of the following is the speed droop for the diesel generator?
A.
~ 3.6%
B.~
3.8% -
C.
4.4%
D.
4.6%
l ANSWER:
C.
PROOF:
Droop = NL - FL
= 1800 - 1720
= 4.4%.
NL 1800 QUESTION:
18-
)
TOPIC:
291004 I
KNOWLEDGE:
Kl.02 QID:
B1821 (P1927)
Which one of the following is an effective method for ensuring that a centrifugal pump remains
- primed and does not become gas bound during operation and after shutdown?
A.
Install an orifice in the discharge piping of the pump.
B.
Install the pump below the level of the suction supply.
C.
Install a check valve in the discharge piping of the pump.
' D.
Install a pump recirculation line from the pump discharge piping to the pump supply.
ANSWER: B.
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
19 TOPIC:
291004 KNOWLEDGE:
Kl.06 QlD:
B2119 (Rev)
Refer to the drawing of an operating cooling water system (see figure below).
Which one of the following will decrease available net positive suction head for the centifugal
. pump?
A.
Adding water to the surge tank to raise level by 10%
B.
Positioning heat exchanger service water valve B more open C.
Positioning pump discharge valve C more open j
D.
Reducing heat loads on the cooling water system by 10%
i ANSWER: C.
A SERVICE SURGE WATER MAKEUPS 74 TANK f
)
M b)"
[][][]LoYos C
A D
j O
C PUMP COOLING WATER SYSTEM f
i 1
USNRC GENERIC FUNDAMENTALS EXAMINATION
. APRIL 1998 BWR-FORM A QUESTION:
20 TOPIC:
291004' KNOWLEDGE:
Kl.11 QID:
B925 (P1921)
Refer to the drawing of a centrifugal pump operating curve (see figure below).
j Which one of the following determines the general shape of the curve from point D to point B?
. A.
The frictional and throttling losses in the piping system as the system flow rate increases B.
The frictional losses between the pump impeller and its casing as the differential pressure (D/P) across the pump increases C.
Pump flow losses due to the decrease in available net positive suction head as the system flow rate mcreases i
D.
Pump flow losses due to back leakage through the clearances between the pump impeller and casing as the D/P across the pump increases ANSWER: A.
4 I
POINT A
/
I U
POINT B EAD POINT D POINT C A
FLOW CENTRIFUGAL PUMP OPERATING CURVE l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A i
QUESTION:
21 TOPIC:
291004 KNOWLEDGE:
Kl.05 QID:
B1619 (Rev)
A multispeed centrifugal pump is operating with a flow rate of 3000 gpm. Which one of the following approximates the new flow rate if the speed is decreased from 3600 rpm to 3000 rpm?
A.
1000 gpm B.
1500 gpm C.
2000 gpm D.
2500 gpm ANSWER: D.
PROOF:
p,3 F
S 2
2 bk S F, 2
F=
2 S i p, 3000(3000) 3600 F = 2500 gpm 2
1 USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
22-
{
TOPIC:
291004 KNOWLEDGE:
Kl.12
)
QID:
B1323 (P1623)
A centrifugal pump is operating at maximum design flow, delivering water through two parallel valves. Valve A is 1/2 open, and valve B is 1/4 open.
Which one of the following will occur if both valves are fully opened?
A.
The pump will immediately operate at shutoff head.
B.
The pump will immediately operate at runout conditions.
C.
The pump available net positive suction head (NPSH) will increase.
D.
The pump required NPS.H will decrease.
ANSWER: B.
i 1
1 l l'
F l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A 1
QUESTION:
23 TOPIC:
291004 KNOWLEDGE:
Kl.13 QlD:
B722 (Rev)
Refer to the drawing of a centrifugal pump operating curve (see figure below).
A centrifugal pump is currently operating at point B. If the pump speed is reduced by one-half, the new operating point will be located on curve
, closer to point
. (Assume that no other changes occur in the system.)
A.
1; D -
B.
2; A C.
1; E D.
2; C ANSWER: A.
j POINT A POINT E curve $
POINT B CURVE 2
/
y POINT C FLOW CENTRIFUGAL PUMP OPERATING CURVE l
l l
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
24 TOPIC:
291004 I
KNOWLEDGE:
Kl.13/Kl.19
'QID:
B1725 (Rev)
Two identical centrifugal pumps (cps) and two identical poritive displacement pumps (PDPs) are cble to take suction on a vented water storage tank and provide makeup water flow to a cooling water system. The pumps are capable of being cross-connected to provide multiple configurations. In single pump alignment, each pump will supply 100 gpm at a system pressure of 1200 psig.
l Given the following information:
Centrifunal Pumns Shutoffhead:
1500 psig Maximum design pressure:
2000 psig Positive Displacement Pumns Maximum design pressure:
2000 psig Which one of the following pump configurations will supply the highest makeup flow rate to the system if system pressure is at 500 psig?
l A.
Two cps in series B.
Two cps in parallel l_
C.
Two PDPs in parallel D.
One PDP and one CP in series (CP supplying PDP)
ANSWER: B.
PROOF:
l Two cps in series results in more than 100 gpm at the reduced system pressure. Two cps in parallel i
results in much more than 200 gpm at the reduced system pressure. Two PDPs in parallel results in approximately 200 gpm. One PDP and one CP in series results in approximately 100 gpm.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A
. QUESTION:
25 1
TOPIC:
291004 KNOWLEDGE:
Kl.16
[)
QlD:
B1919 (Pl726)
An ideal (no slip) reciprocating positive displacement pump is operating in an open system to provide makeup water to a coolant system that is being maintained at 800 psig. The discharge valve of the pump was found to be throttled to 80% open.
If the valve is subsequently fully opened, pump flow rate will and pump head will A.
increase; decrease is, increase; remain constant C.
remain constant; decrease D.
remain constant; remain constant ANSWER: C.
QUESTION:
26 TOPIC:
291005 KNOWLEDGE:
Kl.02 QID:
B1526(P1028)
Which one of the following will result from prolonged operation of ac motor windings at excessively high temperatures?
A.
Decreased elecak.al ground resistance due to breakdown of winding insulation B.
Increased electrical ground resistance due to breakdown of winding insulation C.
Decreased electrical current demand due to reduced counter electromotive force D.
Increased electrical current demand due to reduced counter electromotive force ANSWER: A.
- 22
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
27 i
TOPIC:
291005 KNOWLEDGE:
Kl.03-QID:
New
. A mre. generator is operating on the grid with the following indications:
100 MWe 0MVAR 2,900 amps 20,000 volts If MVAR does not change while real load is increased to 200 MWe, the current supplied by the
. generator will increase to approximately:
A.
I1,600 amps B.
8,200 amps C.
5,800 amps D.
4,100 amps ANSWER: C.
PROOF:
P = / 3 VIpf I = P/(/~3 VIpf)
I = 2 x 10'/(3.46 x 10')
I = 5773.5 amps,
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A
_ QUESTION:
28 TOPIC:
291005 KNOWLEDGE:
Kl.05 QlD:
B1327 (P1827)
Which one of the following describes the motor current during the start of a typical ac motor-driven centrifugal pump with a closed discharge valve?
A.
~ Current immediately increases to the full-load value and then gradually decrecses to the no-load value.
B.
- Cunent immediately increases to the full-load value and then stabilizes at the full-load value.
C.
Current immediately increases to many times the full-load value and then rapidly decreases to the full-load value after several seconds and then stabilizes.
Current m dhtely increases to many times tha full-load value and then rapidly decreases to i
D.
the no-load value after several seconds and the, stabilizes.
ANSWER D.
QUESTION:
29 TOPIC:
291005' KNOWLEDGE:
Kl.07.
QlD:
B929 What is the significance of a power factor of 0.8 when discussing output of a generator?
- A.
80% of the generator output will be converted to useful power.
B.
80% of the energy input to the generator produces useful output.
C.
- This information characterizes the generator as a de generator.
D.
- 11:e relationship between generator output voltage and current can be described as purely resistive.
~
ANSWER: A.
- 24
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
'30
. TOPIC:
291005 KNOWLEDGE:
- Kl.08 QlD:
B1729 (Rev)
A main generator is operating on the grid with the following indications:
600 MWe '
100 MVAR (VARs out) _
13,800 amps 25,000 volts If main generator excitation is decreased, amps will initially and MVAR willinitially-(.
A. -
decrease; increase l
l B.
increase; increase i
C.
decrease; decrease D.
increase; decrease i
j ANSWER: C.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
31 TOPIC:
291006 KNOWLEDGE:
Kl.04 QlD:
B632 Refer to the drawing of an operating water cleanup system (see figure below).
Valves A, B, and D are fully open and valve C is 20% open. All temperatures are currently as shown. Valve C is then opened to 50%.
How will the temperatures at points 3 and 6 be affected?
Point 3 Point 6 A.
Decrease Decrease B.
Decrease Increase C.
Increase Decrease D.
Increase Increase ANSWER: D.
R RN FROM SYSTEM SYSTEM 540*Fi'2 1
A j
450*F HEAT EXCHANGER
,X
=
122*F 4
)
C 250*F1l4 s
l j
COOUNG EXCHANGER WATER l
110*F l
122*F ii7 ION EXCHANGER WATER CLEANUP SYSTEM i
1
- 26
F l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 HWR-FORM A 1
QUESTION:
32 TOPIC:
291006 KNOWLEDGE:
Kl.08 QID:
B2132 (P2133)
Refer to the drawing of a lube oil heat exchanger (see figure below).
The lube oil heat exchanger is in service with the following inlet temperatures:
Lube oilinlet temperature:
120*F Cooling water inlet temperature:
60*F Assuming cooling water flow rate is greater than lube oil flow rate, which one of the following sets of heat exchanger outlet temperatures is possible? (Assume both fluids have the same e.)
p Lube Oil Cooling Water
' Outlet Temp Outlet Temp A.
100*F 100*F B.
90 F 90*F C.
80"F 80 F D.
80*F 100"F ANSWER: C.
PROOF:
C. is the only option that shows a cooling water temp increase that is smaller than the lube oil temp.
decrease. This must be the case since cooling water flow rate is greater than lube oil flow rate.
i Yawm
=_
n-
.... =....
=
1 M
M L
i LUBE OlL HfAT EXCHANGER I
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A i
QUESTION:
33 TOPIC:
291006 L
KNOWLEDGE:
Kl.03 QID:
B2033 (Rev) l A parallel-flow heat exchanger and a counter-flow heat exchanger are being used in the same water-to-water cooling application. Each heat exchanger is identical in construction and each heat exchanger has the same mass flow rates and inlet temperatures.
l Under these conditions, the parallel-flow heat exchanger will have the heat transfer rate because A.
lower; the average AT across the tube walls is smaller B.
lower; the average outlet temperature of the two fluids is lower l
C.
higher; the average AT across the tube walls is greater D.
higher; the average outlet temperature of the two fluids is higher l
ANSWER: A.
i I
I
- 28
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
34 TOPIC:
291006 KNOWLEDGE:
Kl.10 QlD:
B733 Which one of the following changes will result in increased subcooling of the condensate water in the condenser hotwdl?
'A.
Decrease circulating water flow B.
Increase circulating water temperature C.
Decrease the main turbine generator MW load
. D.
Isolate one bay of the condenser circulating water system
- ANSWER: C.
I QUESTION:
35 TOPIC:
291006 KNOWLEDGE:
Kl.16 QlD:
B1234 (P32)
Refer to the drawing of a lube oil heat exchanger (see figure below).
t If scaling occurs inside the cooling water tubes, cooling water outlet temperature will and lube oil outlet temperature will
. (Assume oil and cooling water flow rates remain the same.)
A.
decrease; decrease B.
decrease; increase C.
increase; decrease i
D.
increase; increase ANSWER: B.
I USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A l
)
m c'l
]
b A ?k, Y W
w p' y y ;.':..;_ u wr.. !,
..h%kt,G.'.. f g W
R
=
h LUBEOIL LUBE OIL HEAT EXCHANGER
.30 -
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR--FORM A QUESTION:
36 TOPIC:
291006 KNOWLEDGE:
Kl.13 QlD:
B1536 (Rev)
Which one of the following describes the state of water at 160 psig and 372 *F7 A.
Saturated liquid B.
Subcooled liquid C.
Superheated vapor D.
Mixture ofsaturated liquid and vapor ANSWER: C.
PROOF:
P for 372*F is - 177.6 psia P.,,is 160 psig + 15 = 175 psia P.,, < P, = superheated QUESTION:
37 TOPIC:
291007 KNOWI EDGE:
Kl.01
.QlD:
B737(P935)
A demineralizer is being used in a water purification system. How will accumulation of suspended solids in the demineralizer affect performance of the demineralizer?
A.
The rate of resin depletion will increase.
B.
The number ofion exchange sites will decrease.
C.
The flow rate of water through the demineralizer will increase.
D.
The rate of unwanted ion removal from the system will decrease.
ANSWER: D....
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
38, TOPIC:
291007 KNOWLEDGE:
Kl.05 QID:
B1138 (Rev)
A condensate demineralizer differential pressure (D/P) gauge indicates 4.0 psid at 50% flow. Over the next two days plant power changes have caused condensate flow to vary between 25% and 100%.
Which one of the following combinations of condensate flow and demineralizer D/P, observed during the power changes, indicates an increased accumulation of corrosion pmducts in the demineralizer?
CONDENSATE DEMINERALIZER FLOW D/P (PSID)
A.
100 %
15.0 B.
75 %
9.0 l-
- C.
40 %
3.0 D.
25 %
1.0 l
ANSWER: C.
PROOF:
2 F = N; H - N
@25% flow, D/P should be 1.0 psid H /H = (F /F )2
@40% flow, D/P should be 2.56 psid i 2 i 2 H = H (F /F )2
@75% flow, D/P should be 9.0 psid 2
i 2 i
@l00% flow, D/P should be 16.0 psid Only choice C exceeds the expected D/P.
I l
j l
i 32 -
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
39 1
TOPIC:
291007
)
KNOWLEDGE:
Kl.07
{
QlD:
B2138 i
Which one of the following will decrease the time required for a demineralizer to reduce the ionic impurities in a closed process water system?
A.
Increase the flow rate of the process water from 95 gpm to 105 gpm.
B.
Decrease the temperature of the process water from 110 F to 100"F.
C.
Divert 50% of the process water flow to bypass the demineralizer.
1 D.
Reverse the flow ofprocess water through the demineralizer.
ANSWER: A.
l QUESTION:
40 TOPIC:
291008 KNOWLEDGE:
Kl.04 QID:
B840 (P840)
A typical 120 Vac manual circuit breaker has tripped due to overload. To. class this circuit breaker the handle must be moved from the:
A.
OFF position directly to the ON position; trip latch reset is nel required.
B.
midposition directly to the ON position; trip latch reset is nel required.
l C.
OFF position to the midposition to reset the trip latch, and then to the ON position.
l D.
midposition to the OFF position to reset the trip latch, and then to the ON position.
ANSWER: D.
I 1
l 1 '
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A i
QUESTION:
41 TOPIC:
291008 KNOWLEDGE:
Kl.06 QlD:
New Refer to the drawing of a valve motor control circuit (see figure below) for a valve that is cutrently fully open and has a 10-second stroke time.
Which one of the following describes the valve response if the control switch is taken to the "Close" l
position for two seconds and then released?
A.
The valve will not move.
B.
The valve will close fully.
l C.
The valve will begin to close and then stop moving.
l l
D.
The valve will begin to close and then open fully.
ANSWER: C.
l l
l l
+125 VDC l
Neutral Neutral wi. a
)
%a >
O O
O
... 9......... 9...
O Ki 2, Open Oose Open Case (G)
T
_Lst
__m
_ _m
_ _m
_ _m open h open h
~~
~
open h open h oyes Whos Valw FsBy open Valw Fouy Desed Valw Fupy Valw Fuay Valw Fuly O en M
open l
K2-1 Kl 1 P
_A i
j K1 K2 opes Reisy Gene Relay VALVEMOTOR CONTROL CIRCUIT l
II:
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
42 TOPIC:
291008
- KNOWLEDGE
Kl.07 u
QID:
B842 (P1241)
. A 480 Vac motor is supplied power via an electrical disconnect in series with a circuit breaker.
Which one of the following describes the proper operation to isolate power to the load?
A.
Open disconnect first, then breaker
\\
l B.
Open breaker first, then disconnect l-C.
Open the breaker and disconnect at the same time D. -.
Sequence is not important as long as the motor is operating l
ANSWER: B.
i L
QUESTION:
43 TOPIC:
291008 KNOWLEDGE:
Kl.08 QID:
B2044 (Rev)
A typical main generator is being paralleled to the grid. Generator voltage is slightly higher than grid voltage and the synchroscope is rotating slowly in the clockwise direction. The generator breaker is j
closedjust prior to the synchroscope pointer reaching the 12 o' clock position.
Which one of the following will occur after the breaker is closed?
l l
A.
The breaker will remain closed and the generator will supply only MW to the grid.
B.
The breaker will remain closed and the generator will supply both MW and MVAR to the grid.
C.
The breaker will open due to overcurrent.
D.
The breaker will open due to reverse power.
ANSWER: B.
1 USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
44 TOPIC:
291008 KNOWLEDGE:
Kl.09 QID:
B1943 (P40)
' Loss of breaker control power will cause:
A.
breaker line voltage to indicate zero regardless of actual breaker position.
B.
the remote breaker position to indicate open regardless of actual breaker position.
C.
inability to operate the breaker locally and remotely.
D.
failure of the closing spring to charge following local closing of the breaker.
ANSWER: D.
]
QUESTION:
45 TOPIC:
292001 KNOWLEDGE:
Kl.02 l
QID:
B1345 (Rev)
A neutron that is born 10- seconds after the associated fission event is classified as a j
fission neutron.
A.
spontaneous B.
delayed C.
prompt D.
thermal ANSWER: B.
i 1
1 l
[
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A f
i.
QUESTION:
46 l
TOPIC:
292001 KNOWLEDGE:
Kl.02 QlD:
B2046 (P205)
When comparing a delayed neutron and a pmmpt neutron born from the same fission event, the prompt neutron is more likely to:
A.
be born with a lower kinetic energy.
l B.
cause therrnal fission of a U-235 nucleus.
C.
require a greater number of collisions to become a thermal neutron.
D.
be captured by U-238 at a resonant energy peak between 1 eV and 1000 eV.
ANSWER: C.
QUESTION:
47 TOPIC:
292002 l-KNOWLEDGE:
Kl.09 l
QID:
B1247 Which one of the following combinations of core conditiens at 35% power indicates the least amount of excess reactivity exists in the core?
CONTROL REACTOR RECIR-ROD POSITION CULATION FLOW A.
50% inserted 50%
B.
50% inserted 25 %
- C.
25% inserted' 50 %
D.
25% inserted 25 %
ANSWER: C.
l l
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
48 l.
TOPIC:
292002 l
KNOWLEDGE:
Kl.14
.QID:
B948 (Rev)
I Which one of the following core changes will decrease shutdown margin? Assume no operator actions.
A.
Depletion of fuel during reactor operation B.
Depletion of burnable poisons during reactor operation C.
Buildup of Sm-149 following a reactor power transient D.
Buildup of Xe-135 following a reactor power transient ANSWER: B.
L QUESTION:
49 TOPIC:
292003 KNOWLEDGE:
Kl.04 QID:
B2250 (Rev)
Which one of the following percentages of fission, by fuel, ocurring in a reactor will result in the smallest reactor core effective delayed neutron fraction?
90%
7%
3%
B.
80 %
6%
14 %
C.
70 %
7%
23 %
' D.
60 %
6%
34 %
ANSWER: D.
PROOF:
Pu-239 has the smallest B. Therefore, the fuel that contains the most Pu-239 will have the smallest Beff.
USNRC GENERIC FUNDAMENTALS EXAMINATION -
' APRIL 1998 BWR-FORM A QUESTION:
50 TOPIC:
292003 KNOWLEDGE:
Kl.06 QID:
B1250 (P1548)
I Two reactors are identical in every way except that reactor A is at end of core life and reactor B is at l
the beginning ofcore life. Both reactors are critical at 10*/o power.
l If the same amount of positive reactivity is added to each reactor at the same time, the point of f
adding heat will be reached first by reactor because it has a delayed neutron i
fraction.
(
A.
A; larger l
B.
B; larger C.
A; smaller i
D.
B; smaller ANSWER: C.
I l
. QUESTION:
51 TOPIC:
292003 KNOWLEDGE:
Kl.08/Kl.05 QID:
B1651 (Rev) l During a reactor startup, the intermediate range monitor readings increase from 20% to 40% on the same range in 2 minutes with no operator action. Which one of the following is the average reactor period during the power increase?
A.
173 seconds i
B.
235 seconds C.
300 seconds D.
399 seconds 1
ANSWER: A.
f PROOF:
P=Pe" 0.693 = 120/r o
40 = 20 ei2w' t = _120 = 173 seconds 0.693 2.0 = ei2w, L --
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
52 TOPIC:
292004 KNOWLEDGE:
Kl.04 QID:
B1553 (P1951)
A reactor is operating at 70% power. Which one of the following will directly result in a less negative fuel temperature coefficient? (Consider only the effect of the change in each listed parameter.)
A.
Increase in Pu-240 inventory in the core B.
Increase in moderator temperature C.
Increase in fuel temperature D.
Increase in void fraction ANSWER: C.
REFERENCE:
GE Reactor Theory, p. 4-30 through 4-42 l
l QUESTION:
53 TOPIC:
292008/292004 KNOWLEDGE:
Kl.14/Kl.14 QID:
B272 (Rev)
During a normal power decrease from 100% to 20%, the smallest positive reactivity addition will be caused by the change in:
}
A.
void percentage.
B.
fuel temperature.
C.
xenon concentration.
D.
moderator temperature.
ANSWER: D.
i l
I i
USNRC GENERIC FUNDAMENTALS EXAMINATION
' APRIL 1998 BWR--FORM A l
QUESTION:
54 TOPIC:
292005 KNOWLEDGE:
Kl.04 QID:
B1954 (Rev)
A reactor is operating at equilibrium 20% power. Then reactor power is increased to 40%. As compared to operating conditions at 20%, when the plant stabilizes at 40% power, reactor vessel pressure will be and reactor vessel water temperature will be
.I
. A.
the same; the same f
B.
the same; higher C.
higher; the same D
higher; higher 4
l ANSWER: D.
f I
QUESTION:
55 I
{
i l
DELETED I
i l'
I l l
I USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A
, QUESTION:
56 TOPIC:
292005 KNOWLEDGE:
Kl.09 QID:
New
/
A reactor and plant startup is in progress from a cold shutdown condition. During the heatup phase of the startup, control rod differential reactivity worth (AK/K per inch insertion) becomes l
negative, and during the power increase from 20% to full power, control rod differential reactivity worth becomes negative.
A.
more;less B.
more; more C.
less;less D.
less; more ANSWER: A.
QUESTION:
57 TOPIC:
292005 KNOWLEDGE:
Kl.12 l
QID:
B1757 Which one of the following control rods, when repositioned by 2 notches, will have the smallest effect on axial flux shape?
A.
Deep rods at the center of the core B.
Deep rods at the periphery of the core C.
Shallow rods at the center of the core D.
_ Shallow rods at the periphery of the core i
ANSWER: B.
L l
i i L
p
' USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
58 TOPIC:
292006 KNOWLEDGE:
Kl.03 QID:
B257 (PI859)
The maior contributor to the production of Xe-135 in a reactor that has been operating at full power for 2 weeks is:
A.
the radioactive decay ofiodine.
B, the radioactive decay ofpromethium.
C.
direct production from fission of U-235.
L D.
direct production from fission of U-238.
l ANSWER: A.
l-QUESTION:
59 l
TOPIC:
292006 KNOWLEDGE:
Kl.05 QID:
B658 (P660) l l
A reactor has been operating at 100% power for one week when power is ramped in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 50%.
Which one of the following describes the new equilibrium core xenon concentration?
A.
Remains the same because it is independent of power l.
l B.
More than one-half the 100% value s
C.
Less than one-half the 100% value D.
One-half the 100% value 1
ANSWER: B.
I
- 43
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A 1
QUESTION:
60 TOPIC:
292006 KNOWLEDGE:
Kl.10 QID:
Bil62 A reactor scram occurred from steady state 100% power and a startup is currently in progress.
Which one of the following sets ofinitial startup conditions will require the mmt control rod withdrawal to achieve criticality? (BOC = beginning of fuel cycle; EOC = end of fuel cycle.)
TIME SINCE CORE AGE REACTOR SCRAM A.
BOC 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B.
BOC 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> C,
EOC 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D.
EOC 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> ANSWER: C.
QUESTION:
61 TOPIC:
292006 KNOWLEDGE:
Kl.ll QID:
B2063 (Rev)
A reactor had been operating at 70% power for two weeks when power was increased to 100% over a 2-hour period. To offset core Xe-135 reactivity changes during the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, which one of the following incremental control rod manipulations will be required?
4 A.
Withdraw rods slowly during the entire period.
B.
Withdraw rods slowly at first, then insert rods slowly.
l C.
Insert rods slowly during the entire period.
D.
Insert rods slowly at first, then withdraw rods slowly.
ANSWER: D.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR--FORM A QUESTION:
62 TOPIC:
292006 KNOWLEDGE:
Kl.12 QID:
B2159 (P1063)
A reactor has been operating at 100% power for three weeks when a reactor scram occurs. The core Xe-135 concentration 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the scram will be:
A.
at or approaching a peak value.
B.
approximately the same as at the time of the scram.
C.
less than 1/2 the concentration at the time of the scram and decreasing.
- D.
at least 2 times the concentration at the time of the scram and decreasing.
ANSWER: B.
QUESTION:
63 DELETED i
1 i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
64 TOPIC:
292007 KNOWLEDGE:
Kl.03 QID:
B564 (P264)
Just prior to refueling, control rods are nearly fully withdrawn at 100% power. After refueling, the control rods are inserted much farther into the core at 100% po'wer.
Which one of the following is the reason for the change in full oower control rod position?
A.
Reactivity from power defect at beginning of core life (BOL) is much greater than at end of core life (EOL).
B.
Reactivity from void coefficient at EOL is much greater than at BOL.
C.
The excess reactivity in the core at BOL is much greater than at EOL.
I D.
The integral control rod worth at EOL is much greater than at BOL.
ANSWER: C.
1 l
i i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUES 110N:
65 TOPIC:
292008 KNOWLEDGE:
Kl.03 QlD:
B2069 (Rev)
A reactor startup is in progress with a current K,y of 0.95 and a current stable source range count rate of 120 cps. Which one of the following equilibrium count rates will occur when K,y becomes 0.977
'A.
- 200 cps B.
245 cps C.
300 cps D.
375 cps ANSWER: A.
PROOF:
CR (1 - K ) = CR (1 - K )
i i
2 2
CR = CR, (1 - K,)/(1 - K )
2 2
= 120[(1 - 0.95)/(! - 0,97)]
= 120(0.05/0.03)
= 200 cps USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
66 TOPIC:
292008 KNOWLEDGE:
Kl.04
.QID:
B1665 (Rev)
Refer to the drawing of three 1/M plots (see figure below).
A core refueling is in progress with an installed neutron source. During the early stages of the refueling, reactor criticality would be predicted earliest by curve and could possibly be the result of using nuclear instrumentation that is located too the neutron source.
A.
A; far from B.
A; close to C.
C; far from D.
C; close to ANSWER: A.
1-1M C
B A
i 0
FUEL LOADED 1/M PLOT I
- t.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A
. QUESTION:
67 TOPIC:
292008 KNOWLEDGE:
Kl.08 QID:
B868 (P868)
Which one of the following indicates that a reactor has achieved criticality during a normal reactor startup?
i A.
Constant positive period with no rod motion B.
Increasing positive period with no rod motion l
C.
Constant positive period during rod withdrawal D.
Increasing positive period during rod withdrawal ANSWER: A.
QUEST 10N:
68 TOPIC:
292008 KNOWLEDGE:
Kl.12 QID:
B133 (P1169)
A reactor is critical well below the point of adding heat when a small amount of oositive reactivity is added to the core. If the same amount of negative reactivity is added to the core approximately 1 minute later, reactor power will stabilize at:
A.
the initial power level.
B.
somewhat lower than the initial power level.
C.
somewhat higher than the initial power level.
D.
the suberitical multiplication equilibrium level.
ANSWER: C.
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A
' QUESTION:
69 TOPIC:
292008
- KNOWLEDGE:
Kl.13 QID:
B1769 (Rev)
After taking critical data during a reactor startup, the operator establishes a positive 48-second reactor period to increase power to the raint.of adding heat (POAH). Which one of the following is the approximate amount of reactivity needed to stabilize power at the POAH7 (Assume L =
0.00579.)
A.
-0.10% AK/K B.
-0.12% AK/K C.
-0.01% AK/K D.
'-0.012% AK/K ANSWER: A.
PROOF:
p = [ +.__k_
r 1 + ).T p = 0.00579 1 + (0.1)(48) p = 0.001 = 0.10% AK/K i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
70 TOPIC:
292008 KNOWLEDGE:
Kl.18 l
QlD:
B2072 (P2069)
With a reactor on a constant period of I80 seconds, which one of the following power changes l
' 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:
Pr = P e*
o l'
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)(180) = 0.693(180) = t = 124.8 seconds (In 60/30)(180) = 0.51(180) = t = 124.8 seconds I
l.
I L.
USNRC GENERIC FUNDAMENTALS EXAMINATION
' APRIL 1998 BWR-FORM A QUESTION:
71 TOPIC:
292008 KNOWLEDGE:
Kl 22 QID:
New A plant is operating at 90% power at the end of core life when the turbine control system opens the turbine control valves an additonal i percent. Reactor power will initially:
A.
increase due to positive reactivity addition from the void coefficient only.
B.
increase due to positive reactivity addition from the void and moderator temperature coefficients.
C.
decrease due to negative reactivity addition from the void coefficient only.
D.
decrease due to negative reactivity addition from the void and moderator temperature coefficients.
ANSWER: C.
1 l
QUESTION:
72 TOPIC:
292008 KNOWLEDGE:
Kl.25 QID:
B771 (P770)
Which one of the following is responsible for the negative 80-second stable reactor period experienced shortly after a reactor scram?
I A.
The worth of the inserted control rods B.
The shutdown marginjust prior to the scram C.
The longest-lived delayed neutron precursors D.
The shortest-lived delayed neutron precursors l
l ANSWER: C.
I t
3
)
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
73 TOPIC:
293001 KNOWLEDGE:
Kl.03 QID:
B1174 (Rev)
Refer to the drawing of four identical tank differential pressure level detectors (see figure below).
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 ctmospheric pressure. All level detectors have been calibrated and are producing the same level indication. A ventilation malfunction causes containment structure pressure to decrease to 12 psia.
Which level detectors will produce the lowest level indication?
A.
I and 2 B.
3 and 4 C.
I and 4
-D.
2 and 3
{
ANSWER: C.
l l
i
! L l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A REFERENCE LEG FILL CONNECTION
[
GAS OR VAPOR PRESSURE
/
/
/
WATER L-A-
D/P D/P DETECTOR DETECTOR NO.1 NO. 2
"'I'!!s'CMN
[ GAS OR VAPOR I
7 PRESSURE 0,
WATER j f///bx/
I /
m 22z D/P D/P I
DETECTOR DETECTOR NO. 3 NO. 4 i
TANK DIFFERENTIAL PRESSURE LEVEL DETECTORS i I
I-l USNRC GENERIC FUNDA.MENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
74 TOPIC:
293003 KNOWLEDGE:
Kl.23 QlD:
B1776 (Rev)
Which one of the following is the approximate amount of heat required to convert 2.0 lbm of water rt 100*F and 100 psia to a saturated vapor at 100 psia?
I A.
Il19 Btu B.
Il87 Btu C.
2238 Btu D.
2374 Btu
' ANSWER: C.
PROOF:
Enthalpy of water at 100*F,100 psia = 68.0 Btu /lbm Enthalpy of saturated water at 100 psia = 298.5 Btu /lbm Enthalpy of saturated vapor at 100 psia =
1187.2 Btu /lbm X = 2 lbm (1187.2 Btu /lbm - 68 Btu /lbm)
X = 2(1119.2) Btu l
X = 2238.4 Btu L
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
75 TOPIC:
293003 KNOWLEDGE:
Kl.12 QID:
New Which one of the following describes the effect of removing heat from a steam-water mixture that is in a saturated condition? (Assume the mixture remains saturated.)
A.
Temperature willincrease.
B.
Temperature will decrease.
C.
Quality willincrease.
D.
Quality will decrease.
ANSWER: D.
)
I
- 56 l
l 1
t.
- USNRC GENERIC FUNDAMENTAL S EXAMINATION o
APRIL 1998 BWR-FORM A l
QUESTION:
76 TOPIC:
293004 KNOWLEDGE:
Kl.04 QID:
B1775 Refer to the drawing of an operating steam-jet air ejector (see figure below).
In the figure of an operating steam-jet air ejector, steam flowing from 1 to 2 undergoes a pressure and a velocity A.
increase; decrease
. B.'
increase; increase C.
decrease; decrease D.
decrease; increase ANSWER: D.
1 2 3
4 i
i Skwy
]!f STEAM
' DISCHARGE I
I
% STEAM
$ni{@g j;;
' gh a
^'"
I h
)
I i
3 AIR & STEAM I
l 1 r
L USNRC GENERIC FUNDAMENTALS EXAMINATION i
l APRIL 1998 BWR-FORM A QUESTION:
77 TOPIC:
-293004 KNOWLEDGE:
Kl.13 i
QID:
B1177 (Rev)
A plant is operating at 100% power. Which one of the following describes how and why main J
condenser pressure changes when condenser cooling water flow rate increases significantly?
A.
Decreases because main condenser saturation (shell) temperature decreases B.
Decreases because main condenser condensate subcooling increases C.
Increases because main condenser saturation (shell) temperature decreases
. D.
Increases because main condenser condensate subcooling increases l
ANSWER: A.
l QUESTION:
78 TOPIC:
293005 KNOWLEDGE:
Kl.05 QID:
B1278 A reactor plant was initially operating normally at 90% power when heating steam (supplied by the turbine) to several feedwater heaters was automatically isolated. The plant stabilized and reactor l
power was returned to 90%.
As compared to the initial turbine load, the current turbine load is:
3 A.
higher, because less steam is being extracted from the turbine.
B.
higher, because the steam cycle is less efficient.
C.
lower, because less steam is being extracted from the turbine.
l D.
lower, because the steam cycle is less efficient.
ANSWER: D.
l L.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A L
QUESTION:
79 TOPIC:
293006 KNOWLEDGE:
Kl.13 QID:
B1578 (P926)
Refer to the drawing of four sets of centrifugal pump operating curves (see figure below). Each set of curves shows the results of a change in pump / system operating conditions.
Two identical constant-speed centrifugal pumps are operating in series in an open system when one pump trips.
Which set of operating curves depicts the "before" and "after" conditions described above?
A.
1.
B.
2.
C.
3.
D.
4.
ANSWER: C.
PUMP PUMP HEAD HEAD
/
FLOW FLOW 1.
2.
s PUMP PUMP HEAD HEAD Flow Flow 3.
H
(
CENTRIFUGAL PUMP OPERATING CURVES USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A i
QUESTION:
80 TOPIC:
293006 KNOWLEDGE:
Kl.19 QlD:
B1181 A plant is operating at full power when a 200 gpm reactor coolant leak occurs, which results in a reactor scram and initiation of emergency coolant injection. Reactor vessel pressure stabilizes at 900 psia and all injection pumps are operating with all pump miniflow paths isolated. The shutoff heads for the pumps are as follows:
High pressure coolant injection (HPCI) pumps:
1200 psia Low pressure coolant injection (LPCI) pumps:
200 psia Which pumps must be stopped quickly and why?
A.
LPCI pumps to avoid motor overheating caused by low flow 1
B.
LPCI pumps to avoid pump overheating caused by low flow C.
HPCI pumps to avoid motor overheating caused by high flow
[
D.
HPCI pumps to avoid pump overheating caused by high flow ANSWER: B.
l 1
i
- 60 t
i 1
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
81 l
TOPIC:
293006 i
KNOWLEDGE:
Kl.29 QID:
B1979 (Rev)
A 60 gpm leak has developed in a cooling water system that is operating at 150 psig. Which one of i
the following will be the approximate leak rate when system pressure has decreased to 100 psig?
A.
27 gpm B.
35 gpm C.
40 gpm D.
49 gpm ANSWER: D.
PROOF:
DP=f DP /DP = (flf)*
i 2
i 2 1.225 = 60/f2 f = 60/1.225 2
f = 48.98 gpm 2
1 l
I USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
82 TOPIC:
293007 KNOWLEDGE:
Kl.01 QID:
B882 (P584)
\\
Refer to the drawing of a fuel rod and coolant flow channel at the beginning of core life (see figure below).
What is the primary method of heat transfer through the gap between the reactor fuel and the fuel clad?
A.
Radiation B.
Conduction C.
Convection D.
Natural circulation ANSWER: B.
l P @j :
j CLAD Y
j FUEL PELLET
=
+
TY I
4 m
l a
w l
y COOLANT N COOLANT FLOW 4
F'.OW x
l u
i FUEL ROD AND COOLANT FLOW CHANNEL l t
L
7 I
[
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A i
)
QUESTION:
83 TOPIC:
293007 KNOWLEDGE:
Kl.07 QID:
B2184 (Rev)
Which one of the following pairs of fluids undergoing heat transfer in identical heat exchangers will yield the smallest heat exchanger overall heat transfer coefficient?
A.
Oil to water B.
Air to water C.
Steam to water D.
Water to water ANSWER: B.
- QUESTION:
84 TOPIC:
293007 KNOWLEDGE:
Kl.13 QID:
B2183 (P2185)
The power range nuclear instruments have been adjusted to 100% based on a calculated heat balance.
Which one of the following will result in indicated reactor power being lower than actual reactor power?
A.
The feedwater temperature used in the heat balance calculation was 20*F higher than actual feedwater temperature.
)
B.
The reactor recirculation pump heat input term was omitted from the heat balance calculation.
C.
The steam and feedwater flow rates used in the heat balance calculation were 10% higher than actual flow rates.
D.
The steam pressure used in the heat balance calculation was 50 psi lower than actual steam i
pressure.
i ANSWER: A.
L USNRC GENERIC FUNDAMENTALS EXAMINATION i
APRIL 1998 BWR-FORM A QUESTION:
85 TOPIC:
293008 KNOWLEDGE:
Kl.04 QlD:
New-Subcooled water enters the bottom of a fuel assembly in an operating reactor core. As the water flows upward past the fuel assembly, boiling occurs and the coolant exits the fuel assembly at -
saturation temperature.
If the coolant had remained subcooled, average fuel temperature would have been because boiling is a
_ efficient method of heat transfer.
A.
higher; more B.
higher, less C.
lower; more D.
lower;less ANSWER: A.
QUESTION:
86 TOPIC:
293008 KNOWLEDGE:
Kl.06 QID:
B387 (Rev)
Which one of the following conditions must occur to sustain natural convection in a fluid system?
A.
Subcooling of the fluid
- B.
A phase change in the fluid C.
A density change in the fluid D.
Radiative heat transfer to the fluid ANSWER: C.
I
!fI I j
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
87 TOPIC:
293008 KNOWLEDGE:
Kl.09 QID:
B1486 Refer to the drawing of a pool-boiling curve (see figure below).
Which one of the following regions represents the most unstable heat transfer?
A.
I B.
II C.
III D.
IV ANSWER: C.
I il
! Ill '
IV i
l l
i l
l i
I i
i l
i LOG I
l l
HEAT FLUX j
LOG AT POOL BOILING CURVE i
i l
I, USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
88 TOPIC:
293008 KNOWLEDGE:
Kl.10 QID:
B390 l
The magnitude of the local fuel pin heat flux that is necessary to cause the onset of transition boiling is:
A.
largest at the top of the core and smallest at the bottom.
B.
largest at the bottom of the core and smallest at the top.
C.
largest at the midplane and smallest at the top and bottom.
i i'
D.
smallest at the core midplane and largest at the top and bottom.
i ANSWER: B.
i 1
(,
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
89 TOPIC:
293008 KNOWLEDGE:
Kl.21 QID:
B1689 (Rev)
Given the following conditions:
10 lbm mixture of vapor and liquid i
Steam quality =
40%
Pressure 1,000 psia
=
Which one of the following approximates the void fraction?
)
A.
93.2 %
B.
89.9 %
C.
10.1 %
i D.
6.8%
ANSWER: A.
PROOF:
Void Fraction =
Volume Steam Volume Steam + Volume Water 0.4(0.445961
=
0.4(0.44596) + 0.6(0.02159) 0.178384
=
0.178384 + 0.012954
= 0.178384 0.191338
= 0.9323 = 93.2%
l L i
t
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
90 TOPIC:
293008 KNOWLEDGE:
Kl.29 QID:
B2090 (Rev)
Reactors A and B are identical. Reactor A is operating at 50% power and reactor B is operating at 75% power. Neutron flux is radially and axially peaked in the center ofeach core. Recirculation
{
mass flow rate through each core is the same.
j Compared to the center fuel bundle in reactor A, the center fuel bundle in reactor B has the critical power and the coolant flow rate.
i A.
lower; lower B.
lower; higher C.
higher; lower D.
higher; higher ANSWER: A.
l 1
QUESTION:
91 l
TOPIC:
293008 i
KNOWLEDGE:
Kl.35 QID:
B293 A reactor is shut down with all reactor recirculating pumps stopped. Which one of the following explains why it is important to monitor reactor vessel skin temperatures?
A.
These temperatures provide the best indication of the accuracy of the shutdown reactor water
[
level instruments due to the temperature variance from instrument calibration conditions.
B.
These temperatures provide a backup indication of reactor water level because the skin temperatures detected above vessel water level will be lower than those below vessel water level.
C.
Excessive differential between the upper and lower elevation reactor vessel skin temperatures indicates that thermal stratification is occurring.
D.
Excessive differential temperature between the top and bottom reactor vessel heads will result in excessive thermal stresses in the reactor vessel wall.
ANSWER: C.
o USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A l
QUESTION:
92 TOPIC:
293009 KNOWLEDGE:
Kl.01 QID:
B1092 (Rev)
In a reactor operating at full power, the fuel bundle w ith the lowest power always has the smallest:
A.
critical power ratio.
I t
B.
radial peaking factor.
C.
axial peaking factor.
D.
critical heat flux.
l ANSWER: B.
QUESTION:
93 TOPIC:
293009 KNOWLEDGE:
Kl.13 QID:
B1595 Which one of the following is indicated when the maximum average power ratio (MAPRAT) is greater than 1.07 i
A.
The linear heat generation rate (LHGR) limit has not been exceeded.
B.
The average planar linear heat generation rate (APLHGR) limit has not been exceeded.
C.
The LHGR limit has been exceeded.
D.
The APLHGR limit has been exceeded.
ANSWER: D.
l I
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
94 TOPIC:
.293009 KNOWLEDGE:
Kl.16 QID:
B1995 (Rev)
Refer to the drawing of a fuel rod and coolant flow channel (see figure below) at beginning of core life.
The reactor is shut down with the following parameter values:
T,,oi,,,
= 320 F T w,,,.
= 780*F What would the fuel centerline temperature be under these same conditions at the end of core life if the total fuel-to-coolant thermal conductivity were doubled?
A.
550 F B.
500"F C.
450"F i
]
D.
400 F ANSWER: A.
CLAD ruEL PELLET j
i ws
%s COOLANT COOLANT FLOW Flow s
FUEL ROD AND COOLANT FLOW CHANNEL PROOF:
- Q = UAAT 4
If U doubles, then AT is reduced by 1/2. Initial AT = 460 F, Final AT = 230'F.
Therefore, final fuel temperature = 320 F + 230 F = 550 F.
. t
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
95 TOPIC:
293009 KNOWLEDGE:
Kl.26 QID:
B897 Reactor power will be closest to the critical power if a reactor is operating with a' axial powerdistribution and a recirculation flow. (Assume a constant total reactor power for each of the following core conditions.)
A.
' top-peaked; low B.
top-peaked; high C.
bottom-peaked; low D.
bottom-peaked; high ANSWER: A.
QUESTION:
96 TOPIC:
293009 KNOWLEDGE:
Kl.30 QID:
B1596
. A step increase in reactor power results in a fuel cladding surface temperature increase from 550 F to 580*F at steady state conditions. The fuel thermal time constant is 6 seconds.
Which one of the following is the approximate fuel cladding surface temperature 6 seconds after the power change?
l A.
561"F B.
565 F C.
569 F D.
571*F ANSWER: C.
1.
PROOF:
Tr = T + 0.632(Tr-T)
T, = 550 + 18.96 3
i Tr = 550 + 0.632(580 - 550)
Tr = 569.0 I i
I l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR--FORM A l
QUESTION:
97 i
l l
i DELETED i
QUESTION:
98 TOPIC:
292009 KNOWLEDGE:
Kl.42 QID:
B1297 (Rev)
A plant is operating at 90% power at the end of core life when the turbine control system opens the turbine control valves an additonal 5 percent. Assuming the reactor does not scram immediately, critical power ratio will initially due to a(n) latent heat of vaporization.
A.
increase; increased B.
increase; decreased C.
decrease; increased D.
decrease; decreased ANSWER: A.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 BWR-FORM A QUESTION:
99 TOPIC:
293010
' KNOWLEDGE:
Kl.04 QlD:
New l
Reactor coolant system pressure-temperature limit curves are derived by using a conservative value 1
for the reactor vessel reference temperature for nil ductility transition (RTm).
Early in core life, the assumed value of RT, is than actual RTm; and actual RT, is verified periodically over core life by A.
higher; removing and testing irradiated specimens of reactor vessel material B.
_ higher; inservice inspection and analysis of the reactor vessel wall C.
lower; removing and testing irradiated specimens of reactor vessel material D.
lower; inservice inspection and analysis of the reactor vessel wall 1
ANSWER: A.
QUESTION:
100 TOPIC:
293010 KNOWLEDGE:
Kl.05 Q1D:
B1200(P1898)
Which one of the following is the maior contributor to embrittlement of the reactor vessel?
A.
High-energy fission fragments B.
High operating tempensture C.
High-energy gamma radiation D.
High-energy neutron radiation ANSWER: D.
?-
I UNITED STATES NUCLEAR REGULATORY COMMISSION PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 - FORM A Please Print Name:
Facility:
Docket No.:
Stan 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 ponion of the written licensing examination. All examination papers 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 water reactor (PWR) power plant.
SECTION QUESTIONS
% OF TOTAL SCORE COMPONENTS 1-44 REACTOR THEORY 45 - 72 THERMODYNAMICS 73 - 100 TOTALS 100 i
l L
All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature l l l
t
RULES AND GUIDELINES FOR THE 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.
Fillin the name ofyour facility.
3.
Fill in your individual docket number.
4.
Fill in your start and stop times at the appropnate 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 could also result in severe penalties.
9.
Restroom trips are limited. Only DNE examinee may leave the room at a time. In order to avoid the appearance or possibility ofcheating, avoid all contact with anyone outside of the examination room.
10.
After you have completed the examination, sign the statement on the cover sheet indicating that the l
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.
i l
l
- 12. After turning in your examination materials, leave the examination area, as defined by the proctor.
If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeited.
1 2 -
I GENERIC FUNDAMENTALS EXAMINATION EOUATIONS AND CONVERSIONS HANDOUT SHEET EOUATIONS Q = se 6T P = P 10 sum p
Q = sah P=P,e*
^~^
Q = UAAT CRw = S/(1 - K,y) 3
~
CR (1 - K m) = CR (1 - K n2) i e
2 e
AT "
$ at cire 1/M = CR /CRx N
i 2
2 K,g = 1/(1 - p)
DRW = 9g,/9g p = (K,y-1)/K n F = PA e
SUR = 26.06/r s = pAv r=U P
W,,, = sAPu p
len P 1
E = IR r
11 P = - + 1 + 1,g Eff. = Net Work Out/ Energy In T
t
( = 1 x 10" seconds 2g, g,
(y= 0.1 seconds-'
2 g, = 32.2 lbm.ft/lbf-sec i
CONVERSIONS 6
1 Mw = 3.41 x 10 Btu /hr 1 Curie = 3.7 x 10 dps I hp = 2.54 x 10' Btu /hr 1 kg
= 2.21 lbm i Btu = 778 fl.lbf I gal, = 8.35 lbm 2
"C
= (5/9)( F - 32)
I ft.,, = 7.48 gal F
= (9/5)( C) + 32 USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
1 TOPIC:
191001 KNOWLEDGE:
Kl.01 QlD:
.P1802 (Rev)
A vertical safety valve has a compressed spring assembly that is applying 2500 lbf to the top of the valve disk in opposition to system pressure. System pressure is being exerted on the underside of the valve disk that is 5 inches in diameter.
. Which one of the following is the approximate system pressure at which the safety valve will open?
(Neglect the effect of atmospheric pressure.)
A.
32 psi B.
127 psi C.
.159 psi D.
500 psi ANSWER: B.
PROOF:
F = PA P = F/A j
P = 2500/3.14(2.5)2
" = 2500/19.63 I
P = 127.35 psi i
i l
l i
l
_4
r USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A
(
QUESTION:
2 TOPIC:
191001 KNOWLEDGE:
Kl.03 QID:
- P2102 (Rev)
' Which one of the following statements describes the flow rate characteristics of a typical globe valve in an operating water system?
.i A.
The first 25% of valve disk travel in the open dimetion will produce a smaller change in flow rate than the last 25% of valve disk travel.
B.
The first 25% of valve disk travel in the open direction will produce a greater change in flow rate than the last 25% of valve disk travel.
C.
The first 25% of valve disk travel in the open direction will produce approximately the same I
change in flow rate as the last 25% of valve disk travel.
l l
D.
A globe valve that has been opened to 25% ofvalve disk travel will result in approximately l
25% of full flow rate.
t l
ANSWER: B.
QUESTION:
3-TOPIC:
191001 KNOWLEDGE:
Kl.03 QID:
. New A control valve is most likely to experience cavitation when the valve is almost fully because of a relatively pressure drop across the valve seat.
A.
open;large B.
open; small
. C. -
closed;large D.
closed; small ANSWER: C.
i USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR-FORM A L
l QUESTION:
4 l
TOPIC:
191001 l
KNOWLEDGE:
Kl.03 QlD:
P2004 (Rev)
When comparing globe valves to gate valves, globe valves:
A.
are less effective at throttling flow.
B.
are less effective as pressure regulating valves.
C.
produce a smaller pressure decrease when fully open.
l D.
require less force to open against large differential pressures.
ANSWER: D.
I QUESTION:
5 TOPIC:
191002 i
KNOWLEDGE:
Kl.04 j
QID:
P706 (Rev)
An orifice is being used in an operating cooling water system to measure flow rate. Which one of the following will cause the differential pressure sensed across the orifice to decrease?
A.
System pressure decreases.
B.
System flow rate decreases.
l l
C.
Debris becomes lodged in the orifice.
D.
A leak develops in the low pressure sensing line.
- ANSWER: B.
-6 j
USNRC GENERIC FUNDAMENTALS EXAMINATION
~ APRIL 1998 PWR - FOP.M A 1
QUESTION:
6 l
TOPIC:
191002 KNOWLEDGE:
Kl.05 QID:
P1808 (Rev) t A venturi is used to measure flow rate in a cooling water system. As the water flows from the throat to the discharge of the venturi, water pressure will and volumetric flow rate will
. (Assume water is incompressible.)
A.
increase; remain the same B.
_ increase; increase l
l C.
decrease; remain the same i
D.
decrease; decrease ANSWER: A.
l I i l-
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
,7 TOPIC:
191002 KNOWLEDGE:
Kl.04 QlD:
Pl705 (Rev)
Refer to the drawing of a horizontal pipe elbow (top view) in an operating water system (see figure below).
Three separate bellows differential pressure flow detectors are connected to taps A, B, C, and D as follows:
DETECTOR TAPS AD A and D BD B and D CD C and D
. Assuming zero head loss in this section of pipe, how will the detectors be affected if system flow rate remains the same while system pressure increases from 1000 psig to 1200 psig?
A.
All detectors will indicate higher flow.
B.
Only two detectors will indicate higher flow.
C.
Only one detector will indicate higher flow.
D.
Detector indication will not change.
ANS'VER: D.
tti 8
C ll FLOW b~~
D PlPE ELBOW -TO? VIEW
-8
[
i USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR - FORM A l-QUESTION:
8 TOPIC:
191002 KNOWLEDGE:
Kl.06 QID:
.New Refer to the drawing of a steam generator differential pressure level detector (see figure below).
i l
A reactor coolant system cooldown has resulted in a decrease in steam generator pressure from 900 l:
psia to 400 psia in one hour. Without density compensation of the level instrumentation, at the end of the cooldown, steam generator level indication would indicate than actuallevel l
because the density of the water in the has changed significantly.
A.
higher; steam generator i
.B.
higher; reference leg L
C.
lower; steam generator D.
. lower; reference leg j
i L
' ANSWER: A.
}
l l STEAM n
V i
l l
EQ 2 NO WATER
[
z:2
_z DETECTOR STEAM GENERATOR OtFFERENTIAL PRESSURE LEVEL DETECTOR I t i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A l
- QUESTION:
9 TOPIC:
191002
= KNOWLEDGE:
Kl.08 QlD:
P14 (B510) l' Refer to the drawing of a water storage tank with two differential pmssure level indicators (see figure below).
Indicator 1 was calibrated at 200*F and indicator 2 was calibrated at 100*F. If tank water temperature is 150*F, then:
l A.
indicator 1 and 2 will read the same.
l B.
indicator I will read greater than indicator 2.
C.
indicator 2 will read greater than indicator 1.
I D.
both indicators will be inaccurate, but it is impossible to predict which indicator will read greater.
ANSWER: B.
l TANK OPEN TO ATMOSPHERE f
l WATER
/
l e.
e.
l TANK DIFFERENTIAL PRESSURE LEVEL INDICATORS USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
10 TOPIC:
191002 KNOWLEDGE:
Kl.12 QID:
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.
100 psia.
B.
60 psia.
C.
15 psia.
D.
O psia.
ANSWER: C.
PROOF: 75 psia
~0- 15 psia (atmosphere)
Diaphragm rupture - System pressure not seen.
With diaphragm pressure detector equalized with atmosphere, indicated pressure would be atmospheric or 15 psia.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
11 TOPIC:
191002 l
KNOWLEDGE:
Kl.13 QID:
Pl710 (B1710)
Refer to the drawing of a simple thermocouple circuit (see figure below).
Thermocouple temperature indication is currently 150*F. If a small steam leak occurs that raises both the measuring (hot) junction and reference (cold) junction temperatures by 20 F, the new temperature indication will be:
A.
130*F.
B.
150*F.
C.
170 F.
l D
190 F.
ANSWER: B.
REFERENCE:
P-57,1983, pp. 8.15-8.22 l
\\
t e
a n
(~
l votTAOc MEASURING [ HOT]
ir JUNCTION
)
l REPERENCE [ COLD)
JUNCTION (TEMPERATURE INDICATION) l l
SIMPLE THERMOCOUPLE CIRCulT PROOF:
T,a,,,,a = tw - T,,io if t,,, and T,,ia both increase by 20 F, then Ta,,,,a will not change.
i i-USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
12 TOPIC:
191002 KNOWLEDGE:
Kl.17 QID:
P1312 A reactor is shut down at 100 cps in the source /startup range when a loss of coolant accident occurs.
How will excore source /startup range neutron level indication change as homogeneous core voiding increases from 20% to 100% in a shutdown reactor?
A.
Decreases because less neutron leakage occurs and then increases because more neutrons are available for subcritical multiplication.
B.
Decreases because fewer neutrons are available for subcritical multiplication and then increases because more neutron leakage occurs.
C.
Increases because more neutron leakage occurs and then continues to increase because more neutrons are available for suberitical multiplication.
D.
Increases because more neutron leakage occurs and then decreases because fewer neutrons are available for suberitical multiplication.
i ANSWdR: D.
QUESTION:
13 TOPIC:
191002 KNOWLEDGE:
Kl.18 QID:
P1812 (Rev)
' A gas-filled radiation detector operating in the proportional region is exposed to a constant gamma 1
radiation field. If the applied voltage is decreased but maintained within the proponional region, the l
rate ofion collection will:
l A.
stay approximately the same because all of the primary ions were already being collected at i
the higher voltage.
i l
B.
stay approximately the same because the ion chamber is still operating at saturated l
conditions.
C.
decrease because more primary ions are recombining in the detector prior to reaching the electrodes.
i D.
decrease because fewer secondary ionizations are occurring in the detector.
i ANSWER: D. 1
i j
USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR-FORM A L
QUESTION:
14 TOPIC:
191002 KNOWLEDGE:
Kl.20 l
QID:
P2114 Which one of the following will cause an upscale failure of a boron-trifluoride (BF ) failed fuel 3
detector operating in the proportional region?
A.
The detector chamber has become flooded with water due to leakage around the electrodes.
B.
The detector electrode high voltage power supply output has decreased 5% due to setpoint drift.
C.
A power supply fuse in the amplifier circuit for the neutron monitoring instrument has -
opened.
D.
A temperature rise has caused the gas pressure inside the detector to increase to within 5 psi of design pressure ANSWER: A.
QUESTION:
15 TOPIC:
191003 KNOWLEDGE:
Kl.02 QID:
P1815 (B1016)
If the turbine shaft speed signal used by a typical turbine governor control system fails.high during turbine startup, the turbine governor will cause turbine speed to:
A.
increase, until an upper limit is reached or the turbine trips on overspeed.
B.
increase, until the mismatch with demanded turbine speed is nulled.
C.
decrease, until the mismatch with demanded turbine speed is nulled.
D.
decrease, until a lower limit is reached or turbine steam flow is isolated.
l ANSWER: D.
1 I
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A l
QUESTION:
16 TOPIC:
191003 l
KNOWLEDGE:
Kl.04 QID:
P1315 (B917)
Refer to the drawing of a lube oil temperature control system (see figure below).
l-If the temperature transmitter fails lo.w (Iow temperature output signal), the temperature controller will position the temperature control valve more
, causing the actual heat exchanger lube oil outlet temperature to l
A.
closed; decrease l
l B.
closed; increase i
l C.
open; decrease i
D, open; increase ANSWER: B.
l i
dl TEMPERATURE LUBE TRANSMITTER -
OIL
~ ~ ~ ~ ~ " ~ ~ ~ ~ ~
ON OL I
i i
WA ER
"^
TEMPERATURE CONTROL VALVE
- i LUBE OlL l
)
Luce oil TEMPERATURE CONTROL SYSTEM l
1 l-i i-
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
17' TOPIC:
191003 KNOWLEDGE:
Kl.05 QlD:
P1217 (B1416)
The purpose of a typical valve positioner in a pneumatic control system is to:
A.
provide actual valve position feedback to the valve controller.
B.
position the solenoid valve that supplies air to the valve actuator.
C.
compare valve controller output signal to valve position and adjust valve actuator air supply pressure to position the valve.
l i
D.
compare valve controller output signal to setpoint error, and adjust valve actuator air supply
{
pressure to position the valve.
ANSWER: C.
QUESTION:
18 TOPIC:
191003 KNOWLEDGE:
Kl.06 QID:
B1920 (Rev)
Given the following diesel generator design ratings:
Overspeed trip setpoint:
2000 rpm Operating speed, no load:
1800 rpm Operating speed, fullload:
1720 rpm Which one of the following is the speed droop for the diesel generator?
A.
3.6%
B.
' 3.8%
C.
4.4%
D.
4.6%
ANSWER: C.
i PROOF:
Droop = NL - FL
= 1800 - 1720 l
=4.4%
l
USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR - FORM A i
QUESTION:
19 TOPIC:
191003 KNOWLEDGE:
Kl.09 QlD:
P1016 (Rev) l The level in a drain collection tank is being controlled by an automatic level controller and is initially ct the controller set point. Flow rate into the tank increases, causing tank level to increase. The increasing level causes the controller to throttle open a tank drain valve. After a few minutes, a new, steady-state tank level above the original level is established, with the drain flow rate equal to the supply flow rate.
The controllerin this system uses control.
A.
on-off B.
proportional C.
proportional plus integral D.
proportional plus integral plus derivative ANSWER: B.
QUESTION:
20
' TOPIC:
191004 KNOWLEDGE:
Kl.01 QID:
P421 i
Pump cavitation occurs when vapor hubbles are fonned at the eye of a pump impeller:
A.
when the localized flow velocity exceeds sonic velocity for the existing fluid temperature.
B.
when the localized pressure exceeds the vapor pressure for the existing fluid temperature.
C.
and enter a high pressure region of the pump where they collapse causing damaging pressure pulsations.
D.
and are discharged from the pump where they collapse in downstream piping causing damaging pressure pulsations.
l ANSWER: C.
i l l
USNRC GENE.RIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
21 TOPIC:
191004 l
KNOWLEDGE:
Kl.03 l
QID:
P1927 (B1821) l Which one of the following is an effective method for ensuring that a centrifugal pump remains primed and does not become gas bound during operation and after shutdown?
A.
Install an orifice plate in the discharge piping of the pump.
B, Install a pump recirculation line from the pump discharge piping to the pump supply.
C.
Install the pump below the level of the suction supply.
D.
Install a check valve in the discharge piping of the pump.
ANSWER: C.
QUESTION:
22 t
TOPIC:
191004 KNOWLEDGE:
Kl.04 QID:
P2022 (Rev)
A centrifugal fire water pump takes a suction on an open storage tank and discharges through a fire hose. Which one of the following will cause the pump to operate at shutoff head?
A.
Suction temperature is increased to the point that gas binding occurs.
B.
Suction pressure is adjusted until available net positive suction head is reduced to zero feet.
C.
Pump speed is adjusted to the value at which cavitation occurs.
D.
The fire hose nozzle is raised to an elevation that prevents any flow.
ANSWER: D.
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
23 TOPIC:
191004 KNOWLEDGE:
Kl.06 QID:
P1521 (Rev)
Refer to the drawing of an operating cooling water system (see figure below).
Which one of the following will decrease available net positive suction head for the centifugal Pump?
A.
Adding water to the surge tank to raise level by 10%
B.
Positioning heat exchanger service water valve B more open C.
Positioning pump discharge valve C more open D.
Reducing heat loads on the cooling water system by 10%
ANSWER: C.
A SERVICE O
SURGE WATER t
MAKEUPS TANK r
\\
l N
b"
]
] LO S
C A
D k
O PUMP l
COOLING WATER SYSTEM.
I i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A I
QUESTION:
24
' TOPIC:
191004 KNOWLEDGE:
Kl.09
~QlD:
P1823 (Rev)
Refer to the drawing of a cooling water system and the associated centrifugal pump operating curve (see figure below).
Pumps A and B are identical single-speed centrifugal pumps and both pumps are operating. If pump
{
B trips, after the system stabilizes, system flow rate will be:
j
(
A.
more than one-half the original flow.
i B.
one-half the original flow.
l I
C.
the same; only the pump head will change.
j D.
less than one-half the original flow.
ANSWER: A.
I
__r suRoE TANK HEAT EXCHANGER FROM HEAT -
W LOADS j
HEAT-
/
PUMP A
-" o PUMP 8 COOUNG WATER SYSTEM l
PUMP l
HEAD l
[
CENTRIFUGAL PUMP OPERATING CURVE 9
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
25 TOPIC:
191004 KNOWLEDGE:
Kl.14 QID:
P723 (Rev)
Refer to the drawing of a centrifugal pump operating curve (see figure below).
A centrifugal pump is currently operating at point B. If the pump speed is reduced by one-half, the new operating point will be located on curve
, closer to point
. (Assume that no other changes occur in the system.)
A.
1;D B.
2; A C.
1; E D.
2; C ANSWER: A.
j POINT A L
I POINT E CURVE 1 PotNT 5 EA CURVE 2 l
/
j point C l
FLOW CENTRIFUGAL PUMP OPERATING CURVE l l
USNRC GENERIC FUNDAMENTALS EXAMINATION i_
APRIL 1998 PWR-FORM A QUESTION:
26 TOPIC:
191004 KNOWLEDGE:
K1.22 QID:
P826 (B1123)
If the discharge valve of a reciprocating positive displacement pump is throttled toward the closed direction, pump flow rate will and pump head will
. (Assume " ideal" pump response.)
A.
remain constant; increase B.
remain constant; remain constant C.
decrease; increase D.
decrease; remain constant ANSWER: A.
QUESTION:
27 TOPIC:
191005 KNOWLEDGE:
Kl.02 QID:
P1528 (B1126)
Continuous operation of a motor at rated load with a loss of required cooling to the motor windings will eventually result in-A.
cavitation of the pumped fluid.
B.
failure of the motor overcurrent protection devices.
C.
breakdown of the motorinsulation.
D.
phase current imbalance in the motor and overspeed trip actuation.
ANSWER: C.,
i i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A f
1 QUESTION:
28 I
TOPIC:
191005 KNOWLEDGE:
Kl.03
.QlD:
PS29 (Rev) i A ma n generator is operating on the grid with the following indications:
600 MWe 100 MVAR (VARs out) 13,800 amps-l 25,000 volts t
If main generator excitation is decreased, amps will initicily and MVAR willinitially A.
decrease; increase B.
increase; increase l
l C.
decrease; decrease D.
increase; decrease ANSWER: C.
l I
I l
1 l
23 -
J
[
I USNRC GENERIC FUNDAMENTALS EXAMINATION i
APRIL 1998 PWR-FORM A f
I' QUESTION:
29 TOPIC:
.191005 KNOWLEDGE:
Kl.04 QlD:
P1429 (Rev) i i
A multispeed centrifugal pump is operating with a flow rate of 3000 gpm. Which one of the following approximates the new flow rate if the speed is decreased from 3600 rpm to 3000 rpm?
l l
A.
1000 gpm
- B.
1500 gpm C.
2000 gpm D.
2500 gpm
/
l ANSWER: D.
PROOF:
p,3 F
S 2
2 bk S F' 2
F=
2 S,
I p, 3000(3000) 3600 F = 2500 gpm 2
i
- 24 l.
USNRC CoENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
30 TOPIC:
191005 KNOWLEDGE:
Kl.05
.QlD:
P1827 (B1327)
Which one of the following describes the motor current during the start of a typical ac motor-driven centrifugal pump with a closed discharge valve? (Assume the pump does not trip.)
l A.
Current immediately increases to the full-load value and then gradually decreases to the no-load value.
l-B.
Current immediately increases to the full-load value and then stabilizes at the full-load value.
i C.
Current immediately increases to many times the full-lcad value and then rapidly decreases to.
the no-load value after several seconds and then stabilizes.
R D.
Current immediately increases to many times the full-load value and then rapidly decreases to j
the full-load value after several seconds and then stabilizes.
l ANSWER: C.
I QUESTION:
31 TOPIC:
191005 KNOWLEDGE:
Kl.06 QlD:
P231 (B328)
)
Which one of the following is the basis for the restriction on the number of starts that a large ac motor may be subjected to within a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period? '
A. '
Prevent excessive torsional stresses on the motor shaft l
B.
Prevent excessive arcing and degradation of motor breaker contacts C.
Prevent excessive heat buildup within the motor windings D.
Prevent excessive wear of motor thrust bearings
' ANSWER: C.
l-
)
- 1 i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
32 TOPIC:
191006 KNOWLEDGE:
K1.04 QID:
P1032 (B1031)
Refer to the drawing of an operating water cleanup system (see figure below).
Valves A, B, and C are fully open. Valve D is 20% open. All temperatures are as shown. Valve D is then opened to 100%.
The temperature at point:
A.
3 willincrease.
B.
4 will decrease.
C.
5 will decrease.
D.
7 will increase.
ANSWER: B.
RETURN FROM SYSTEM SYS EM
'b 540*F4'2 1
A
>0 450*F HEAT EXCHANGER X
122*F C
250*F1!4 5
HEAT 9h*F COOLING EXCHANGER 6
WATER 110*F 122*Fi'7 i
ION EXCHANGER WATER CLEANUP SYSTEM
. USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
33 TOPIC:
191006 KNOWLEDGE:
Kl.07 QID:
New A parallel-flow heat exchanger and a counter-flow heat exchanger are being used in the same water-to-water cooling application. Each heat exchanger is identical in construction and each heat j
exchanger has the same mass flow rates and inlet temperatures.
Under these conditions, the parallel-flow heat exchanger will have the heat transferrate because i
A.
higher; the average AT across the tube walls is greater B.
higher; the average outlet temperature of the two fluids is higher C.
lower; the average AT across the tube walls is smaller D.
' lower; the average outlet temperature of the two fluids is lower
. ANSWER: C.
QUESTION:
34
. TOPIC:
191006 KNOWLEDGE:
Kl.08 QID:
P1632(B832)
A water-to-water counter-flow heat exchanger is operating with single-phase conditions and a constant specific heat for each liquid. Which one of the following will decrease the heat transfer between the two liquids?
l.
A.
The flow rate of the colder liquid is decreased by 10%.
l B.
The flow rate of the hotter liquid is increased by 10%.
l C.
The inlet temperature of both liquids is decreased by 20*F.
L
.D.
The inlet temperature of both liquids is increased by 20'F.
l
- ANSWER: A.
f l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
35 TOPIC:
191007 KNOWLEDGE:
Kl.01 QID:
P2235 (Rev)
A condensate demineralizer differential pressure (D/P) gauge indicates 4.0 psid at 50% flow. Over l
the next two days plant power changes have caused condensate flow to vary between 25% and 100%.
l Which one of the following combinations of condensate flow and demineralizer D/P, observed during the power changes, indicates an increased accumulation of corrosion products in the demineralizer?
CONDENSATE DEMINERALIZER FLOW D/P (PSID)
A.
100 %
15.0 B.
75 %
9.0 C.
- 40%
3.0 D.
25% '
l.0 ANSWER: C.
PROOF:
2 F = N; H = N
@25% flow, D/P should be 1.0 psid i
H /H = (F /F )2
@40% flow, D/P should be 2.56 psid i 2 i 2 H = H (F /F )2
@75% flow, D/P should be 9.0 psid 2
i 2 i
@l00% flow, D/P should be 16.0 psid Only choice C exceeds the expected D/P.
l l
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A l
QUESTION:
36 l
TOPIC:
191007 KNOWLEDGE:
Kl.06 QID:
P736 A demineralizer is being used in a water purification system. How will accumulation of suspended i
solids in the demineralizer affect the performance of the dcmineralizer?
A.
The rate of resin depletion will increase.
B.
The number ofion exchange sites will decrease.
C.
The flow rate of water through the demineralizer will increase.
D.
'Ihe rate of unwanted ion removal from the system will decrease.
ANSWER: D.
QUESTION:
37 TOPIC:
191007 KNOWLEDGE:
Kl.14 QID:
P1335 The plant is operating at 70% stable power level when the temperature of reactor coolant letdown passing through a baron-saturated mixed bed ion exchanger is increased 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; decreased B.
decrease; increased C.
increase; decreased D.
increase; increased ANSWER: C.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
38 TOPIC:
191008 KNOWLEDGE:
Kl.02 QlD:
P1339 Which of the following local circuit breaker indications provides the most reliable information for l
determining whether a circuit breaker is open or closed?
A.
Overcurrent trip flags and loadside ammeter B.
OPEN/ CLOSED mechanical flag indication and loadside voltmeter C.
OPEN/ CLOSED indicating lights and overcurrent trip flags D.
Loadside ammeter and OPEN/ CLOSED indicating lights ANSWER: B.
3 QUESTION:
39 i
TOPIC:
191008 KNOWLEDGE:
Kl.03 QID:
P118 Which one of the following results from a loss of control power to a breaker supplying a motor?
i A.
Motor ammeter indication will be zero regardless of actual breaker position.
B.
Breaker position will remotely indicate closed regardless of actual position.
C.
Breaker will trip open due to the actuation ofits protective trip device.
D.
Charging motor will nel recharge the closing spring after the breaker closes.
l ANSWER: D.
I i
i a
f l l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
40 TOPIC:
191008 l
KNOWLEDGE:
Kl.04 QlD:
P2041 l
- Two identical 1000 Mw electrical generators are operating in parallel supplying the same electrical l
bus. The generator output breakers also provide identical protection for the generators. Generator A and B output indications are as follows:
I Gene'rator A Generator B 4160 Volts 4160 Volts 60.2 Hertz 60.2 Hertz 50 M'N 100 Mw 25 MVAR (out) 50 MVAR (out)
A malfunction causes the voltage regulator setpoint for generator B to slowly increase continuously toward a maximum of 4400 volts. If no operator action is taken, which one of the following l
describes the current indications for generator A7 A.
Current will decrease continuously until the output breaker for generator A trips on reverse l
power.
B.
Current will decrease continuously until the output breaker for generator B trips on reverse power.
)
C.
Current will initially decrease, and then increase until the output breaker for generator A trips on overcurrent.
D.
Current will initially decrease, and then increase until the output breaker for generator B trips on overcurrent.
ANSWER: D.
l I
I i
['
}
USNRC GENERIC FUNDAMENTALS EXAMINATION
)
APRIL 1998 PWR-FORM A
{
QUESTION:
41 TOPIC:
191008 KNOWLEDGE:
Kl.06 i
QID:
P2239 (Rev)
Refer to the drawing of a valve motor control circuit (see figure below) for a valve that is currently fully closed and has a 10-second stroke time.
1
.Which one of the following describes the valve response if the control switch is taken to the "Open" I
position for two seconds and then released?
A.
The valve will not move.
B.
The valve will open fully.
l C.
The valve will begin to open and then stop moving.
D.
The valve will begin to open and then close fully.
ANSWER: B.
+125 VDC Neutral Neutral m a==>
m,* a*=>
so s0 0
0 O
O O
Kl.2 _ Open M~ """ ~O%"
Close
{g}
T
_IE1
_ _IE2
_IE3
_IE4
_LS5
,s. ~
--o.s. -
o,e. -
,e. m o
o,e. -
o Valve Fuuy open Valve Fou Gesed Valve Fuuy Valve FmWy Valve Fouy r
open NJ open
/ K2-1
/ K1-1 4-K1 K2 Open Relay Osse Relay VALVE MOTOR CONTROL CIRCUIT l
l l
l l
l.
USNRC GENERIC FUNDAMENTALS EXAMINAT10N APRIL 1998 PWR - FORM A QUESTION:
42 l
l l
l l
DELETED 1
1 i
QUESTION:
43 l
TOPIC:
191008 KNOWLEDGE:
Kl.08 QID:
Pl741 (Rev)
' A typical main generator is being paralleled to the grid. Generator voltage is slightly higher than grid voltage and the synchroscope is rotating slowly in the clockwise direction. The generator breaker is closed just prior to the synchroscope pointer reaching the 12 o' clock position.
I Which one of the following will occur after the breaker is closed?
l A.
The breaker will remain closed and the generator will supply only MW to the grid.
l-B.
The breaker will remain closed and the generator will supply both MW and MVAR to the grid.
l C.
The breaker will open due to overcurrent.
l D.
The breaker will open due to reverse power.
ANSWERfB.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
44 TOPIC:
191008 KNOWLEDGE:
Kl.ll QID:
P1044 The following indications are observed in the control room for a nonnally-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.
QUESTION:
45 TOPIC.
192001 KNOWLEDGE:
Kl.02 QlD:
P1545 (Rev)
A neutron that is born 10 '8 seconds after the associated fission event is classified as a fission neutron.
A.
delayed B.
prompt C.
thermal D.
spontaneous ANSWER: A.
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
46 TOPIC:
192002 KNOWLEDGE:
Kl.08 QID:
P2046 A reactor is shutdown with the reactor vessel head removed for refueling. The core is covered by 23 feet of water at a temperature of 100*F and a boron concentration of 2000 ppm.
Which one of the following will increase Keff?
A.
An unrodded spent fuel assembly is removed from the core.
B.
Refueling water temperature increases to 105*F.
C.
A new neutron source is installed in the core.
D.
Excore nuclear instmmentation is repositioned to increase source range count rate.
ANSWER: B.
QUESTION:
47 TOPIC:
192002 KNOWLEDGE:
Kl.10 QlD:
Pl747 (Rev)
Which one of the following core changes will decrease shutdown margin? Assume no operator actions.
A.
Depletion of fuel during reactor operation B.
Depletion of burnable poisons during reactor operation C.
Buildup of Sm-149 following a reactor power transient D.
Buildup of Xe-135 following a reactor power transient l
ANSWER: B.
USNRC GENERIC FUNDAMENTALS EXAMINATION '
APRIL 1998 PWR - FORM A l
. QUESTION:
48 l
TOPIC:
192003' KNOWLEDGE:
- Kl.07
.QlD:
P2249 (Rev)
Which one of the following percentages of fission, by fuel, ocurring in a reactor will result in the l
smallest reactor core effective delayed neutron fraction?
90 %
7%
3%
B.
80%
6%
14 %
C.
70%
7%
23 %
D.
60 %
6%
34 %
ANSWER: D.
PROOF:
Pu-239 has the smallest B. Therefore, the fuel that contains the most Pu-239 will have the smallest Beff.
QUESTION:
49 TOPIC:
192003 KNOWLEDGE:
Kl.05-QlD:
P648 (Rev)
During a reactor startup, reactor power increases from 1E-8% to 2E-8% in 2 minutes with no operator action. Which one of the following is the average reactor period during the power increase?
A.
~ 173 seconds
- B.
- 235 seconds C.
300 seconds D.
399 seconds ANSWER: A'.
PROOF:
P = P,e*
0.693 = 120/t 2 = e'2*'
t = _120 = 173 seconds 0.693
)
1 USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
50 TOPIC:
192004 KNOWLEDGE:
Kl.06 QID:
P951 During a reactor coolant system (RCS) cooldown, positive reactivity is added to the core (assuming a negative moderator temperature coefficient). This is partially due to:
A.
an increase in the resonance escape probability.
I B.
a decrease in the resonance escape probability.
C.
an increase in the thermal utilization factor.
D.
a decrease in the thermal utilization factor.
ANSWER: A.
QUESTION:
51 TOPIC:
192004 KNOWLEDGE:
Kl.09 QlD:
P552 As reactor coolant boron concentration is reduced, differential boron reactivity worth (AK/K per ppm) becomes:
A.
less negative due to the increased number of water molecules in the core.
B.
less negative due to the decreased number of boron molecules in the core.
C.
more negative due to the increased number of water molecules in the core.
D.
more negative due to the decreased number of boron molecules in the core.
ANSWER: D.
l
. USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR - FORM A QUESTION:
52 TOPIC:
192004 i
KNOWLEDGE:
Kl.07 l
QID:
New i
Refer to the drawing of microscopic cross section for absorption versus neutron energy for a resonance peak in U-238 (see figure below).
If fuel temperature increases, the area under the curve will and negative reactivity will be added to the core because A.
increase; neutrons of a wider range of energies will be absorbed by U-238 B.
increase; more neutrons will be absorbed by U-238 at the resonance neutron energy C.
remain the same; neutrons of a wider range ofenergies will be absorbed by U-238 D.
remain the same; more neutrons will be absorbed by U-238 at the resonance neutron energy ANSWER: C.
a b
h 20 L
l NEUTRON ENERoY l -
t
(
~
l f
USNRC GENERIC FUNDAMENTALS EXAMINATION i
l APRIL 1998 PWR - FORM A QUESTION:
53 l
TOPIC:
192004 4
KNOWLEDGE:
Kl.12 l
QID:
P1753 (Rev) l l
Given the following initial parameters:
l Total power coeflicient
=-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 Which one of the following is the final RCS boron concentration required to support decreasing plant power from 80% to 30% by boration/ dilution with 10 inches ofinward control rod motion?
(Assume no change in xenon reactivity.)
A.
425 ppm B.
475 ppm l
C.
525 ppm D.
575 ppm ANSWER: D.
PROOF:
AK/K from rods = 10" x (-0.025% AK/K/in) = -0.25% AK/K AK/K from P.D. = -50% x (-0.020% AK/K/%) = +1.0% AK/K Total AK/K = AK/K rods + AK/Km = -0.25% AK/K + 1.0% AK/K =
+0.75%AK/K Boron reactivity needed to balance reactivity change from power and rods is
-0.75%AK/K i
-0.75% AK/K
-0.010% AK/K/ ppm = 75 ppm boron increase 500 + 75 ppm = 575 ppm USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
54 TOPIC:
192005 KNOWLEDGE:
Kl.03 QID:
P1054 A reactor is operating at end of core life with a steady state 50% power level when the operator withdraws a group of control rods for 5 seconds. (Assume turbine load remains constant and the reactor does not scram / trip.)
Actual reactor power will stabilize -
the initial power and coolant temperature will stabilize the initial temperature.
A.
at; at B.
at; above C.
above; at D.
above; above ANSWER: B.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A l
QUESTION:
55 TOPIC:
192005 KNOWLEDGE:
Kl.05 QlD:
P1554 (B1057)
A control rod is positioned in a reactor with the following neutron flux parameters:
Core average thermal neutron flux = 1 x 10 2 n/cm -see i
2 Control rod tip thermal neutron flux = 5 x 10 n/cm -sec 2
2 If the control rod is slightly withdrawn such that the control rod tip is located in a thermal neutron flux of 1 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 B.
4 C.
10 D.
100 ANSWER: B.
PROOF:
2 CRW =
SVC (9up2Pupi)*
CRW
/
2 CRW (9,,,,/,,,,)2 9
i CRW f (1 x 10"/5 x 10 )2 i2 2
CRW (1 x 10:2 i
/1 x 10 )2 i2 CRW
,4 2
CRW I
2 CRW2 = CRW (4) i 4 '
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
56 TOPIC:
192005 KNOWLEDGE:
Kl.07 QlD:
New
' A reactor and plant startup is in progress from a cold shutdown condition. During the RCS heatup phase of the startup, control rod differential reactivity worth (AK/K per inch insertion) becomes negative, and during the complete withdrawal of the initial bank of control rods, control rod differential reactivity worth becomes A.
more; more negative and then less negative B.
more; less negative and then more negative C.
less; more negative during the entire withdrawal D.
less; less negative during the entire withdrawal ANSWER: A.
QUESTION:
57 TOPIC:
192005 KNdWLEDGE:
Kl.14 QID:
Pl757 Control rod insertion limits are established for power operation to:
A.
provide adequate shutdown margin after a reactor scram.
B.
minimize the worth of a postulated dropped control rod.
C.
maintain a negative moderator temperature coefficient in the reactor.
D.
ensure sufficient positive reactivity is available to compensate for the remaining power defect.
ANSWER: A.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
58 TOPIC:
192006 KNOWLEDGE:
Kl.01 QID:
P2058 (B2061)
A fission product poison can be differentiated from all other fission products in that a fission product poison:
A.
will be produced in direct proportion to the fission rate in the core.
B.
will remain radioactive for thousands ofyears after the final reactor criticality.
C.
will depress the power production in some core locations and cause peaking in others.
D.
will migrate out of the fuel pellets and into the reactor coolant via pinhole defects in the clad.
ANSWER: C.
QUESTION:
59 TOPIC:
192006 KNOWLEDGE:
Kl.06 QlD:
New Which one of the following explains why Xe-135 oscillations are a concern?
A.
They can adversely affect core power distribution and can prevent a reactor startup following a reactor trip.
B.
They can adversely affect core power distribution and can require operation below full rated power.
. C.
They can cause rapid reactor power changes and can prevent a reactor startup following a reactor trip.
D.
They can cause rapid reactor power changes and can require operation below full rated power.
ANSWER: B.
t-f.'
~USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
60 TOPIC:
192006.
L KNOWLEDGE:
Kl.06 QlD:
P2160 (Rev)
A reactor had been operating at 70% power for two weeks when power was increased to 100% over a 2-hour period. To offset Xe-135 reactivity changes during the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, which one of the following incremental control rod manipulations will be required?
A.
Withdraw rods slowly during the entire period.
i B.
Withdraw rods slowly at first, then insert rods slowly.
C.
Insert rods slowly during the entire period.
D.
Insert rods slowly at first, then withdraw rods slowly.
. ANSWER: D.'
-QUESTION:
61 TOPIC:
192006 KNOWLEDGE:
Kl.07
.QlD:
P1358 (B1361)
A reactor has been operating at 75% power for two months. A manual reactor trip is required for a l 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 reactoris 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 ifcriticality is rescheduled for hours after the trip.
A.
50%;8 B.'
50 %; 16 C.
100 %; 8 D.
100 %;16 ANSWER: B.
r
- 44 '-
4
USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR - FORM A QUESTION:
62 TOPIC:
192006 KNOWLEDGE:
Kl.11 QlD:
P1462 l
A reactor has been operating at 100% power for two weeks. Power is then decreased over a 1-hour period to 10%.
i Assuming manual rod control, which one of the following operator actions is required to maintain a constant reactor coolant temperature at 10% power during the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />?
A.
Add negative reactivity during the entire period B.
Add positive reactivity during the entire period C.
Add positive reactivity, then negative reactivity D.
Add negr.tive reactivity, then positive reactivity ANSWER: C.
QUESTION:
63 TOPIC:
192006 KNOWLEDGE:
Kl.12 i
QlD:
P663 (Rev) i Following a reactor trip, negative reactivity from xenon-135 initially:
A.
increases due to xenon production from the decay ofiodine-135.
j B.
increases due to xenon production from the spontaneous fission of uranium.
C.
decreases due to xenon removal by decay.
D.
decreases due to the reduction in xenon production directly from fission.
}
ANSWER: A.
I USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
64 TOPIC:
192007 KNOWLEDGE:
Kl.01 QlD:
pl664 Burnable poisons are installed in a new reactor core instead of using a larger soluble boron concentration to:
A.
. prevent boron precipitation during normal operation.
B.
establish a more negative moderator temperature coefficient.
C.
minimize the distortion of the neutron flux distribution caused by soluble boron.
D.
allow the loading ofexcessive reactivity in the form of higher fuel enrichment.
ANSWER: B.
\\,
I 4gl' f
il USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
65 l
TOPIC:
192008 i
KNOWLEDGE:
Kl.01 QID:
P1665 During a reactor startup, the first reactivity addition caused the count rate to increase from 20 to 30 i
cps. The second reactivity addition caused the count rate to increase from 30 to 60 cps. Assum i
i was 0.97 prior to the first reactivity addition.
Which one of the following statements describes the magnitude of the reactivity additions?
A.
The first reactivity addition was 50% larger than the second.
B.
The second reactivity addition was 50% larger than the first.
C.
The first and second reactivity additions were approximately the same.
D.
There is not enough data given to determine the relationship ofreactivity values.
ANSWER: C.
PR.OOF:
Assume k = 0.97 pi = AK/K = (K -K )/K i
2 i 2
Gi = 1-L pi = 0.01/0.98 CR 1-K 2
i pi = 0.0102 AK/K K = 1 - Gi G.K )
2 i
CR2
= 1 - 2D (1-0.97) 30 K = 0.98 2
2 = 1-L K = 0.99 2
3 CR 1.K 3
2 p2 = AK/K = (K -K )/K 2 2 3
K = 1 - G2 (1-K )
3 2
CR p2 = 0.01/0.99 3
l-
= 1 - 39 (1-0.98) p2 = 0.0101 AK/K 60
- l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
66 i
TOPIC:
192008 KNOWLEDGE:
Kl.04 Q1D:
P566 (Rev)
A reactor startup is in progress with a current K,y of 0.95 and a current stable source of 120 cps. Which one of the following stable count rates will occur when K,y becomes 0.9 A.
200 cps B.
245 cps C.
300 cps D.
375 cps ANSWER: A.
PROOF CR (1 - K ) = CR (I ~ K )
i i
2 2
CR = CR '(1 - K,)/(1 - K )
2 i
2
= 120[(1 - 0.95)/(1 - 0.97)]
= 120(0.05/0.03)
= 200 cps j! '
l i:
4 Na.
I-USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
67 TOPIC:
192008 l
KNOWLEDGE:
Kl.04 QID:
Pl770 (Rev)
Refer to the drawing of three 1/M plots (see figure below).
A core refueling is in progress with an installed neutron source. During the early stages of the refueling, reactor criticality would be predicted earliest by curve and could possibly be the result of using nuclear instrumentation that is located too the neutron source.
A.
A; far from B.
A; close to C.
C; far from D.
C; close to ANSWER: A.
1-i 1M C
B A
O FUEL LOADED 1/M PLOT ?
)
USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR-FORM A L
QUESTION:
68 l
TOPIC:
192008 KNOWLEDGE:
Kl.07 QlD:
P970 An estimated critical rod position (ECP) has been calculated for a reactor startup to be performed 15 i
l hours after a trip from 100% power equilibrium conditions. Which one of the following conditions would cause the actual critical rod position to be highcr than the predicted critical rod position?
4 A.
- A 90% value for reactor power was used in the ECP calculation.
B.
Reactor criticality is achieved approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> earlier than anticipated.
C.
Steam generator pressures are decreased by 100 psijust prior to criticality.
' D.
Current boron concentration is 10 ppm lower than the value used in the ECP calculation.
ANSWER: B.
i l..
l l
QUESTION:
69 TOPIC:
192008 KNOWLEDGE:
Kl.10 i
QID:
P1870
' A reactor startup is in progress following a one-month shutdown. Upon reaching criticality, the operator establishes a positive 80 second period and stops rod motion.
l After an additional 30 seconds reactor power will be and reactor period will be
- (Assume reactor po_wer remains below the point of adding heat.)
l A.
constant; constant l
. B.
constant; increasing C.
increasing; constant -
D.
increasing; increasing ANSWER: C.
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A i
QUESTION:
70 l
TOPIC:
192008 KNOWLEDGE:
Kl.15 l
QlD:
P670 (Rev)
After taking critical data during a reactor startup, the operator establishes a positive 48-second l
reactor period to increase power to the point of adding heat (POAH). Which one of the following is l
the approximate amount of reactivity needed to stabilize power at the POAH? (Assume Lg =
0.00579.)
l
.A.
-0.10% AK/K B.
-0.12% AK/K C.
-0,01% AK/K D.
-0.012% AK/K ANSWER: A.
PROOF:
p = f* + B l
t 1+h p = 0.00579 1 + (0.1)(48) p = 0.001 = 0.10% AK/K l
i L
i l t
f l
USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR-FORM A l
QUESTION:
71 l
TOPIC:
192008 i
KNOWLEDGE:
Kl.20 QID:
P571 A reactor startup is in progress and criticality has just been achieved. After recording critical rod height, the operator withdraws control rods for 20 seconds to establish a 1 DPM startup rate (SUR).
One minute later (prior to the point of adding heat) the operator inserts the same centrol rods for 30 seconds.
During the insertion, the SUR will become:
l 1
A.
zero during the entire period of control rod insertion.
i B.
negative after the control rods pass through the critical rod height.
C.
negative just as the control rods pass through the critical rod height.
D.
negative prior to control rods passing through the critical rod height.
ANSWER: D.
QUESTION:
72 TOPIC:
192008 KNOWLEDGE:
Kl.21 i
QID:
P1570 (Rev)
A plant is operating at 90% power at the end of core life with manual rod control when a turbine control system malfunction opens the turbine control valves an additional 5 percent. Reactor power willinitially:
A.
increase due to reduced neutron absorption in the moderator.
1 B.
increase due to reduced neutron leakage out of the core.
C.
decrease due to increased neutron absorption in the moderator.
D.
decrease due to increased neutron leakage out of the core.
ANSWER: B.
l i
USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR - FORM A 1-QUESTION:
73 TOPIC:
193001 KNOWLEDGE:
Kl.03 QID:
P1673 (Rev)
Refer to the drawing of four identical tank differential pressure level detectors (see figure on next page).
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 Etmospheric pressure. All level detectors have been calibrated and are producing the same level indication. A ventilation malfunction causes containment structure pressure to decrease to 12 psia.
l Which level detectors will produce the lowest level indication?
A.
I and 2 B.
3 and 4 l
'C.
I and 4 D.
2 and 3 ANSWER: C l
l l
i l t
f USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A r
REFERENCE LEG FILL CONNECTION g,
f GAS OR VAPOR -
PRESSURE V' //
l
/
/ WATER j
D/P D/P DETECTOR DETECTOR NO.1 NO. 2 REFERENCE LEG FILL CONNECTION Q
GAS OR VAPOR
-t-PRESSURE l
'Vf/
/
/ WATER i
i
/p
/
D/P D/P DETECTOR DETECTOR NO. 3 NO. 4 TANK DIFFERENTIAL PRESSURE LEVEL DETECTORS t
r USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
74 TOPIC:
193003 KNOWLEDGE:
Kl.08
.QlD:
New Which one of the following describes the effect of removing heat from a steam-water mixture that is in a saturated condition? (Assume the mixture remains saturated.)
A.
Temperature will increase.
B.
Temperature will decrease.
i C.
Quality willincrease.
D.
Quality will decrease.
ANSWER: D.
l t-l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
75 i_
TOPIC:
193003 KNOWLEDGE:
Kl.25 QID:
P1775 (Rev)
Which one of the following is the approximate amount of heat required to convert 2.0 lbm of water et 100*F and 100 psia to a saturated vapor at 100 psia?
A.
I119 Btu B.
Il87 Btu l
C.
2238 Btu D.
2374 Btu ANSWER: C.
PROOF:
Enthalpy of water at 100 F,100 psia = 68.0 Btu /lbm Enthalpy of saturated water at 100 psia = 298.5 Btu /lbm Enthalpy of saturated vapor at 100 psia =
1187.2 Btu /lbm X = 2 lbm (1187.2 Btu /lbm - 68 Btu /lbm)
X = 2(1119.2) Btu X = 2238.4 Btu i
l r
i i -
1 USNRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1998 PWR-FORM A i
QUESTION:
76 TOPIC:
193004 KNOWLEDGE:
Kl.11 QID:
P1076 l
Which one of the following is an advantage of condensate depression in the main condenser?
A.
Increased secondary cycle efficiency l
B.
Increased inventory in the main condenser hotwell C.
Increased feedwater temperature entering the steam generators D.
Increased net positive suction head available to condensate pumps l
ANSWER: D.
i l
l l
i i
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A 1
l QUESTION:
77 TOPIC:
193004 KNOWLEDGE:
Kl.15 QlD:
P1577 (Rev)
A heatup and pressurization of the reactor coolant system (RCS) is in progress following a
. maintenance shutdown. RCS pressure is 800 psia with a steam bubble in the pressurizer.
Pressurizer power-operated relief valve (PORV) tailpipe temperature has been steadily rising. The pressurizer vapor space contains 96.0% quality saturated steam and PORV downstream pressure is l
20 psia.
Assuming PORV leakage is an ideal throttling process, which one of the following will be the approximate PORV tailpipe temperature and phase of escaping fluid if a PORV is leaking by?
A.
254*F, saturated B.
254 F,superheated C.
228'F,-. saturated D.
228 F,superheated ANSWER: B.
PROOF:
h
,,,g.y - 1170 BTU /lbm Using Mollier Diagram,1170 BTU /lbm at 20 psia results in a superheated vapor at - 254"F. 228'F is based on T, for 20 psia.
l 1 l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A
' QUESTION:
78 TOPIC:
193005 KNOWLEDGE:
Kl.03 l
~QID:
P478 To achieve maximum secondary plant efficiency, feed water should enter the steam generator (S/G) and the pressure difference between the S/G and the condenser should be as as possible.
A.
close to saturation; small I
B.
close to saturation; great C.
as subcooled as practical; small D.
as subcooled as practical; great t
ANSWER: B.
l _-
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
79 l
TOPIC:
193006 i
KNOWLEDGE:
Kl.05 j
QlD:
P380 (Rev)
A 60 gpm leak has developed in a cooling water system that is operating at 150 psig. Which one of l
the following will be the approximate leak rate when system pressure has decreased to 100 psig?
A.
27 gpm B.
35 gpm C.
40 gpm i
D.
49 gpm ANSWER: D.
l PROOF:
DP=f' DP /DP "(flf)'
i 2
i 2 l.225 = 60/f 2
f = 60/1.225 2
f = 48.98 gpm 2
1 i
i 60 -
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A
- QUESTION:
80 TOPIC:
193006 KNOWLEDGE:
Kl.ll Q1D:
P1482 (Rev)
Refer to the drawing of a cooling water system in which both pumps A and B are operating and the pump discharge valve is currently 50% open (see figure below).
If pump A is cavitating, which one of the following will reduce or eliminate cavitation in pump A7 A.
Stopping pump B B.
Positioning the discharge valve to 75% open C.
Lowering the water level in the surge tank by 2 feet D.
Decreasing heat exchanger service water flowrate by 10%
ANSWER: A.
P 12:
.sLr.
W w
LOADS t=1 fa 9
'do PUMP A P
P.
COOUNG WATER SYSTEM 1 i
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A QUESTION:
81 TOPIC:
193006
- KNOWLEDGE:
Kl.06 QlD:
P1480 Reactor coolant system (RCS) hot leg temperature is 520*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 $tst occurin the hot leg?
A.
950 to 901 psig B.
900 to 851 psig C,
850 to 801 psig D.
- 800 to 751 psig -
ANSWER: D.
1 QUESTION:
82 TOPIC:
193006 KNOWLEDGE:
Kl.12 QID:
P982 A density-compensated flow instrument is being used to measure mass flow rate in a steam system.
If the pressure of the steam decreases, indicated mass flow rate will: (Assume volumetric flow rate is constant.)
i-A.
increase for all steam conditions.
i B.
decrease for all steam conditions.
C.
increase, but only if the steam is saturated (not superheated).
D.' ~
decrease, but only if the steam is saturated (not superheated).
ANSWER: B.
I USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
83 TOPIC:
193006 KNOWLEDGE:
Kl.15 QID:
Pl784 (Rev) 1 i
Two identical centrifugal pumps (cps) and two identical positive displacement pumps (PDPs) are I
cble to take suction on a vented water storage tank and provide makeup water flow to a cooling water system. The pumps are capable of being cross-connected to provide multiple configurations. In single pump alignment, each pump will supply 100 gpm at a system pressure of 1200 psig.
Given the following information:
Centrifugni Pumps Shutoffhead:
1500 psig Maximum design pressure: 2000 psig Positive Disolacement Pumos Maximum design pressure: 2000 psig
.I Which one of the following pump configurations will supply the highest makeup flow rate to the system if system pressure is at 500 psig?
A.
Two cps in series B.
Two cps in parallel C.
Two PDPs in parallel D.
One PDP and one CP in series (CP supplying PDP)
ANSWER: B.
PROOF:
Two cps in series results in more than 100 gpm at the reduced system pressure. Two cps in parallel results in much more than 200 gpm at the reduced system pressure. Two PDPs in parallel results in epproximately 200 gpm. One PDP and one CP in series results in approximately 100 gpm.
1 I
t
- j
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
84 TOPIC:
193007 KNOWLEDGE:
Kl.04 QID:
P2184 (Rev)
- Which one of the following pairs of fluids undergoing heat transfer in identical heat exchangers will yield the smallest heat exchanger overall heat transfer coefficient?
A.
Water to water B.
Steam to water C.
Air to water D.
Oil to water ANSWER: C, PROOF:
Air has the lowest thermal conductivity of any listed substance.
QUESTION:
85 TOPIC:
193007 KNOWLEDGE:
K1.06 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 beingless than indicated reactor power?
A.
The reactor coolant pump heat input term is omitted from the calorimetric calculation.
j B.
The steam and feedwater flow rates used in the calorimetric calculation are lower than actual j
flow rates.
C.
The steam pressure used in the calorimetric calculation is higher than actual steam pressure.
D.
The feedwater temperature used in the calorimetric calculation is higher than actual feedwater temperature.
r i
ANSWER: A.
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
86 TOPIC:
193008 KNOWLEDGE:
Kl.02 QlD:
New Subcooled water enters the bottom of a fuel assembly in an operating reactor core. As the water flows upward past the fuel assembly, boiling occurs and the coolant exits the fuel assembly at saturation temperature.
l If the coolant had remained subcooled, average fuel temperature would have been because
- boiling is a efficient method ofheat transfer.
1 i
A.
higher; more B.
higher;less C.
lower; more D.
lower;less ANSWER: A.
f l
l )-
l.
(-
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR-FORM A r
- QUESTION:
87 TOPIC:
193008 KNOWLEDGE:
Kl.05 l
QID:
P1889 (Rev)
A plant is operating with the following initial conditions:
Reactor power is 45% 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 decrease 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 with no rod motion.
C.
The operator increases reactor coolant boron concentration by 5 ppm with no control rod motion.
D.
Core Xe-135 builds up in proportion to the axial and radial power distribution with automatic i
rod control.
ANSWER: B.
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i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
88 TOPIC:
193008 KNOWLEDGE:
Kl.06 QlD:
P2187 Which one of the following will be the initial cause of fuel damage if a fuel rod exceeds the critical heat flux at 100% power?
A.
Exessive fuel clad temperature B.
Excessive fuel pellet temperature C.
Excessive fuel rod internal pressure D.
Excessive fuel rod thermal stress ANSWER: A.
QUESTION:
89 i
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I USNRC GENERIC FUNDAMENTALS EXAMINATION l
I APRIL 1998 PWR - FORM A QUESTION:
90 l
TOPIC:
193008 KNOWLEDGE:
Kl.16 QlD:
P391 (B1989)
Refer to the drawing of a fuel rod and coolant flow channel at beginning of core life (see figure below).
l At100 eactor power, the createst temperature difference in a fuel channel radial temperature profile will occur across the: (Assume the temperature profile begins at fuel centerline.)
A.
fuel centerline to fuel surface.
B.
fuel to-clad gap.
C.
zircaloy cladding.
D.
flow channel boundary (laminar) layer.
ANSWER: A.
l
-r%
r CLAD FUEL PELLET c
%W "D
Y I
l P
5T k
??
l COOLANT
$4 COOLANT
$ sl FLOW p
FLOW i
i FUEL ROD AND COOLANT FLOW CHANNEL i
I !
l l
l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
91 TOPIC:
193008 KNOWLEDGE:
Kl.10 QlD:
Pil90 A reactor is operating at 100% steady-state power at the end of core life with all control rods fully withdrawn. At what axial location in a typical fuel assembly will the muimum departure from nucleate boiling ratio occur?
A.
At the top of the fuel assembly B.
At the bottom of the fuel assembly C.
Between the bottom and midplane of the fuel assembly D.
Between the midplane and the top of the fuel assembly
{
ANSWER: B.
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USNRC GENERIC FUNDAMENTALS EXAMINATION
' APRIL 1998 PWR-FORM A QUESTION:
92 TOPIC:
193008 KNOWLEDGE:
Kl.21 QID:
P1692 (Rev)
A reactor is shut down with natural circulation core cooling. Decay heat generation is equivalent to 1.0% rated thermal power. Core AT has stabilized at 13 *F.
When decay heat generation decreases to 0.5% rated thermal power, core AT will be approximately:
A.
4*F.
B.
6*F.
C.
8 'F.
D.
10"F.
ANSWER: C.
PROOF:
AT i/2, Q In AT = Q 2a, AT, _
Qi AT D,
2 2
(
AT AT
- i 2
(D /D )
i2 AT
- 2 (1/.5)2a 2*
1.587 AT = 8.2 F 2
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L USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QIJESTION:
93 TOPIC:
193008 KNOWLEDGE:
Kl.23 QlD:
P1591 i
A reactor had been operating at a constant power level for the last two weeks when a loss of all ac power occurred, thereby causing a scram and a loss of forced reactor coolant flow. Natural circulation reactor coolant flow developed and stabilized 30 minutes after the scram.
Which one of the following combinations ofinitial reactor power and oost-seram steam generator pressure will result in the highest stable natural circulation flow rate 30 minutes after the scram?
INITIAL POST-SCRAM REACTOR STEAM GENERATOR POWER PRESSURE A.
100 %
1100 psia -
B.
100 %
1000 psia C.
25 %
1100 psia D.
25 %
1000 psia ANSWER: B.-
REFERENCE:
P-63, pp.14-20 and 14-21 l
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USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
94 i
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l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
95 TOPIC:
193009 KNOWLEDGE:
Kl.07 Q1D:
P2296 (Rev)
Refer to the drawing of a fuel rod and coolant flow channel at beginning ofcore life (see figure below).
The reactor is shut down with the following parameter values:
Ta,,
= 320*F T,,,,,, no,
= 780*F What would the fuel centerline temperature be under these same conditions at the end of core life if the total fuel-to-coolant thermal conductivity were doubled?
A.
550*F
- B.
500 F C.
450 F D.
400*F ANSWER: A.
h-eLAo FUEL PELLET
%s r%Y ms rmP I
COOLANT COOLANT FLOW FLOW gs FUEL ROD AND COOLANT FLOW CHANNEL I
l PROOF:
Q = UAAT If U doubles, then AT is redu::ed by 1/2. Initial AT = 460"F, Final AT = 230"F.
Therefore, final fuel temperature = 320*F + 230"F = 550"F.
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
96 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.
A compressive stress rather than a tensile stress across the vessel wall B.
Performing a 50*F/hr cooldown at 1600 psia rather than a 50*F/hr cooldown at 1200 psia 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: B.
i i
QUESTION:
97 TOPIC:
193010 KNOWLEDGE:
Kl.04 QlD:
New i
Reactor coolant system pressure-temperature limit curves are derived by using a conservative value for the reactor vessel reference temperature for nil ductility transition (RTuor).
Early in core life, the assumed value of RTuor is than actual RTuor; and actual RTuor is verified periodically over core life by A.
higher; removing and testing irradiated specimens of reactor vessel material B.
higher; inservice inspection and analysis of the reactor vessel wall C.
lower; removing and testing irradiated specimens of reactor vessel material l
D.
lower; inservice inspection and analysis of the reactor vessel wall 1
1 ANSWER: A.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
98 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 heatup followed by a rapid pressurization B.
A rapid cooldown followed by a rapid pressurization C.
A rapid depressurization followed by a rapid heatup.
D.
A rapid depressurization followed by a rapid cooldown ANSWER: B.
QUESTION:
99 TOPIC:
193010 KNOWLEDGE:
Kl.05 QID:
P1699 (B1800) l Two identical reactors have been in operation for the last 10 years. Reactor A has experienced 30 heatup/cooldown cycles and has an average power capacity of 60%. Reactor B has experienced 40 l
heatup/cooldown cycles and has an average power capacity of 50%.
l l
Which reactor will have the lowest reactor vessel nil-ductility transition temperature?
l A.
Reactor A due to the fewer number of heatup/cooldown cycles B.
Reactor A due to the higher average power capacity C.
Reactor B due to the greater number of heatup/cooldown cycles D.
Reactor B due to the lower average power capacity ANSWER: D. i l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1998 PWR - FORM A QUESTION:
100 TOPIC:
193010 KNOWLEDGE:
Kl.07 QID:
P1000 An uncontrolled cooldown is a brittle fracture concern because it creates a large stress et the wall of the reactor vessel.
i A.
tensile; inner B.
tensile; outer C.
compressive; inner D.
compressive; outer ANSWER: A.
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