ML20141D962
| ML20141D962 | |
| Person / Time | |
|---|---|
| Issue date: | 05/19/1997 |
| From: | Debra Mccain NRC (Affiliation Not Assigned) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9705200251 | |
| Download: ML20141D962 (126) | |
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UNITED STATES -
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20616 4001 o,s.
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MAY 19199[
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NOTE T0:
Document Control Desk
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FROM:
Debbie McCain, Licensing Assistant Division of Reactor Controls and Human Factors Operating Licensing Branch
SUBJECT:
APRIL 1997 GENERIC FUNDAMENTALS EXAMINATION (GFE)
Enclosed please find the April, 1997 GFF examination and answer key to be placed in the PDR.
If you have any questions I can be contacted at
'415-1065.
ld TYM Debbie McCain, Licensing Assistant Division of Reactor Controls and Human Factors Operating Licensing Branch Enclosure-As stated 200069 D
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UNITED STATES NUCLEAR REGULATORY CONNISSION BOILING WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 - FORM A Please Print Name:
Facility:
Docket No.:
Start Time:
Stop Time:
INSTRUCTIONS-TO CANDIDATE 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 starts.
This examination applies to a typical boiling water teactor (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.
l Applicant's Signature
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, a RULES AND GUIDELINES FOR THE fENERIC FUNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:
1.
Print your name in the blank provided on the cover sheet of the examination.
2.
Fill in the name of your facility.
3.
Fill in your individual docket number.
4.
Fill in your start and stop times at the appropriate time.
5.
Two aids are provided for your use during the examination:
(1)
An equations and conversions sheet contained within the examination copy, and (2)
Steam tables provided by your proctor.
6.
Place your answers on the answer sheet provided.
Credit will only be given for answers properly marked on this sheet.
Follow the instructions for filling out the answer sheet.
7.
Scrap paper will be provided for calculations.
j 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 lintited.
Only ONE examinee may leave the room at a time.
In order to avoid the appearance or possibility of cheating, avoid all contact with anyone outside of the examination room.
1
- 10. Af ter you have completed tha 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. 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.
- 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.
, l
GENERIC FUNDAMENTALS EXANINATION 1
l EQUATIONS AND CONVERSIONS HANDOUT SHEET EOUATIONS 4
sc AT P = P 108*O
=
j o
p P = P e ("
.Q=
sah j
o A = A e-^*
c Q = UAAT CRsfo = S / (1 - K,g g )
.3
- Ci'*
CR (1 - K rri) = CR (1 - K rra) 2 e
2 e
1 2
AT = sgot cire 1/M = CR /CRx j
2 4
l K rr = 1/ (1 - p)
DRW = $ ip /
2 e
t ave l
p=
I K.g f
- 1) /K rt F = PA o
SUR = 26.06/T g = pg9
- P
= sAPu i
I =
3 A,g g p
)
E = IR f*
3 p=+
T 1 + A,g,I Eff. = Net Work Out/ Energy In (W-f) + g (z2 U(P - P) +
z2)
=0 f* = 1 x 10-' seconds 2
2 2ge gc A.tr = 0.1 seconds-1 32.2 lbm-ft/lbf-sec2 gc
=
CONVERSIONS 3.41 x 105 Btu /hr 1 Curie 1 Mw
=
2 3.7 x 10o dps
=
2.54 x 103 Btu /hr 1 kg 1 hp 2.21 lbm
=
=
l 1 Btu =
778 ft-lbf 1 gal..., =
8.35 lbm j
(5/9) ( F - 32) 1 f t '..t.,
C
=
7.48 gal j
=
(9/5)( C) + 32 F
=
1 I !
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORN A QUESTION:
1 Which one of the following statements describes the flow rate characteristics of a typical gate valve in an operating water system?
A.
The first 25% of valve disk travel in the open direction will produce a smaller change in flow rate than the last 25% of j
valve disk travel.
i i
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 1
valve disk travel.
C.
The first 25% of valve disk travel in the open direction will produce approximately the same change in flow rate as the last 25% of valve disk travel.
D.
A gate valve that has been opened to 25% of valve disk travel will result in approximately 25% of full flow rate.
i QUESTION:
2 1
A. typical limitorque motor-operated valve is being used in an emergency core cooling system (ECCS) application.
The declutch lever has been operated and released and the valve is being manually / locally closed by a technician as required by a surveillance test procedure.
During operation of the valve handwheel an ECCS actuation signal is received that is designed to energize the valve motor and open the valve.
How will the valve be affected by the actuation signal?
A.
The handwheel will disengage and the valve will automatically open.
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 open.
D.
The handwheel will remain engaged and the valve will continue to close.
4_
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
3 Refer to the drawing of a typical safety valve (see figure below).
The component indicated by the solid arrow is used by the operator to manually:
A.
rachet open the safety valve.
B.
pop open the safety valve.
C.
gag shut the safety valve.
D.
determine the position of the safety valve.
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I SAFETY VALVE USNRC CENERIC FUNDAMENTALS EXAMINATION I
APRIL 1997 BWR - FORM A QUESTION:
4 Refer to the drawing of a valve cutaway-view (see figure below).
Which one of the following describes the type of valve shown?
A.
Rising-stem gate valve B.
Rising-stem globe valve C.
Nonrising-stem gate valve i
D.
Nonrising-stem globe valve i
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NW,
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A 4
VALVE CUTAWAY-VIEW I
1 _
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
5 1
l How will a typical motor-operated valve respond to a' loss of l
electrical power?
A.
Open fully' l
B.
Close fully l
C.
Remain as is l
D.
Move to 50% open l
l l
l QUESTION:
6 Which one of the following flow devices produces the largest l
unrecoverable head loss when used in an operating fluid system?
A.
Venturi i
B.
Flow nozzle i
C.
Pipe elbow D.
Orifice i
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U2NRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A t
QUESTION:
7 Refer to the drawing of two tank differential pressure (D/P) level indicators (see figure below).
t l
Two D/P level indicators are installed on a large water st(rage l
tank.
Indicator No. 1 was calibrated at 200 F water temperature and indicator No. 2 was calibrated at 100"F water temperature.
l Assuming both indicators are on scale, which indicator will indicate the lower 3avel?
i A.
Indicator 1 at all water temperatures l
B.
Indicator 2 at all water temperatures J
C.
Indicator 1 below 150*F, indicator 2 above 150 F D.
Indicator 2 below 150 F, indicator 1 above 150 F l
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WATER l
l TANK DIFFERENTIAL PRESSURE LEVEL INDICATDRS i
l.
_ _ _ _ ~ _
USNRC CENERIC FUNDAMENTALS EXAMINATION l
APRIL 1997 BWR - FORM A J
QUESTION:
8
)
Refer to the drawing of a reactor vessel differential pressure i
level detector (see figure below).
Which one of the following events will' result in a reactor vessel level indication that is greater than actual level?
A.
The reference leg water flashes to steam.
B.
The reactor pressure increases by 50 psia.
C.
The variable leg breaks and completely drains.
D.
The temperature surrounding the reference leg decreases by 30 F.
REACTOR VESSEL CONDENSI AMBER STEAM y
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l' EQUAllZING VALVE b 'T f/
j P//
fzzzj D/P OETECTOR REACTOR VESSEL DIFFERENTIAL PRESSURE LEVEL DETECTOR
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F USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A L
QUESTION:
9 A centrifugal pump is taking suction from the bottom of a vented cylindrical storage tank that contains 100,000 gallons of water at 60*F.
A pressure gauge at the inlet to the pump indicates 40 4
psig.
Over the next several days storage tank temperature.
increases to 90*F with no change in tank water level and no change in head loss in the pump suction line.
Which one of the following is the current approximate pressure at the inlet to the pump?
A.
39.8 psig B.
37.4 psig
/
C.
34.6 psig 1
D.
31.2 psig QUESTION:
10 Which one of the following parameters requires square root compensation when measured by differential pressure detectors?
A.
Reactor vessel level B.
Condenser vacuum C.
Reactor vessel pressure 1
D.
Recirculation pump flow rate l
i USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
11 Refer to the drawing of a simple thermocouple circuit (see figure below).
Circuit temperature indication is currently 350*F.
If a small steam leak occurs that raises reference (cold) junction temperature by 20"F, the new temperature indication will be:
(Assume measuring junction temperature remains constant.)
A.
310*F.
B.
330 F.
C.
370 F.
D.
390 F.
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v0LiaoE NRING [H09 ir avNCTmN
)
REPERENCE [ COLD]
po g gg JUNCTION (TEMPERATURE NOCATON)
. :n SIMPLE THERMOCOUPLE CIRCUlT QUESTION: 12 A cooling water system is operating at a steady-state flow rate of 500 gpm with 60 psid across the flow transmitter venturi.
If cooling water flow rate is increased to 1000 gpm, differential pressure across the flow transmitter venturi will be approximately:
A.
85 psid.
B.
120 psid.
C.
240 psid.
D.
480 psid.
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USNRC CENERIC FUNDAMENTALS EXAMINATION
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APRIL 1997 BWR - FORM A QUESTION:
13 The reactor scrammed due to a loss-of-coolant accident I hour i
ago.
To verify adequate reactor vessel water level, the source range monitors (SRMs) are inserted.
As the SRMs enter the core, l
count rate begins to increase and then stabilizes.
i l
If the SRMs enter a voided section of the core, count rate will j
suddenly:
A.
decrease due to decreased fast fission.
B.
decrease due to increased neutron leakage.
C.
increase due to increased neutron migration length.
D.
increase due to decreased moderator neutron absorption.
QUESTION:
14 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 of ion 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 i
the detector.
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USNRC CENERIC FUNDAMENTALS EXAMINATION
~
APRIL 1997 BWR - FORM A QUESTION:
15 In a proportional controller, the term " offset" refers to the difference between the:
A.
control point and setpoint.
B.
control point and proportional band.
C.
deadband and setpoint.
D.
deadband and proportional band.
l l
t i
QUESTION:
16 l
Which one of the following describes the response of a direct 1
acting proportional-integral controller, operating in automatic, to an increase in the controlled parameter above the controller I
setpoint?
l A.
The controller will develop an output signal that continues to increase until the controlled parameter equals the controller setpoint, at which time the output signal becomes constant.
l B.
The controller will develop an output signal that will remain l
-directly proportional to the difference between the i
controlled parameter and the controller setpoint.
C.
The controller will develop an output signal that continues to increase until the controlled parameter equals the controller setpoint, at which time the output signal becomes zero.
D.
The controller will develop an output signal that will remain directly proportional to the rate of change of the controlled parameter.
l I
i,
USNRC CENERIC FUE N ALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
17-An air-operated isolation valve requires 3,200 pounds-force from its diaphragm actuator and 4 inches of stem travel for proper i
operation.
The area of the actuator diaphragm is 160 square inches.
What is the minimum air pressure (rounded to the nearest psig) l required for proper valve operation?
l l
A.
20 psig B.
40 psig l
C.
60 psig D.
80 psig i.
l QUESTION:
18 1
Which one of the following will result in immediate cavitation of a centrifugal pump operating at normal rated flow?
A.
Recirculation flow path is aligned.
R Recirculation flow path is isolated.
C.
Pump suction valve is fully closed.
D.
Pump discharge valve is fully closed, l
l k
I
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
19 Refer to the drawing of an operating cooling water system (see figure below).
l Which one of the.following will increase available net positive l
suction head for the centrifugal pump?
A.
Draining the surge tank to decrease level by 10%
B.
Positioning heat exchanger service water valve B more closed r
C.
Positioning pump discharge valve C more closed l
D.
Positioning pump suction valve D more closed l
i h
A 5
CE SURGE Ep MAKEUPS 74 TANK W
i i
J HEAT LOADS C
A D
O
- k l
PUMP l
COOLING WATER SYSTEM J
i
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USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
20 Which one of the following specifies the proper pump discharge valve position and the basis for that position when starting a large. centrifugal pump?
I A.
Discharge valve fully open to reduce duration of motor starting current B.
Discharge valve throttled to reduce duration of motor starting current i
C.
Discharge valve fully open to ensure adequate pump net positive suction head D.
Discharge valve throttled to ensure adequate pump net positive suction head 1
4 QUESTION:
21 Which one of the following describes centrifugal pump operating parameters at shutoff head?
A.
High discharge pressure, low flow, low power demand B.
High discharge pressure, high flow, low power demand C.
Low discharge pressure, low flow, high power demand D.
Low discharge pressure, high flow, high power demand
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USNRC CENERIC FUNDAMENTALS EXANINATION APRIL 1997 BWR - FORM A QUESTION:
22 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 the pump below the level of the suction supply.
B.
Install an orifice in the discharge piping of the pump.
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.
l QUESTION:
23 A typical single-stage radial-flcw centrifugal pump is being returned to service following maintenance on its ac motor.
Which one of the following will occur when the pump is started if two j
of the three motor power leads were inadvertently swapped during restoration?
l A.
The motor breaker will trip on overcurrent.
B.
The motor will not turn and will emit a humming sound.
C.
The pump will rotate in the reverse direction with reduced or no flow rate.
D.
The pump will rotate in the normal direction with reduced flow rate.
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USNRC EENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
24 An ideal (no slip) reciprocating positive displacement pump is operating in an open system to provide makeup water to a reactor coolant system that is being maintained at 2200 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 B.
remain constant; decrease C.
increase; remain constant 3-D.
remain constant; remain constant i
1 QUESTION:
25 Which one of the following describes the proper location for a relief valve that will be used to prevent exceeding the design
)
l pressure of a positive displacement pump and associated piping?
A.
On the pump suction piping upstream of the suction isolation
)
l valve l
B.
On the pump suction piping downstream of the suction I
isolation valve C.
On the pump discharge piping upstream of the discharge isolation valve l
L D.
On the pump discharge piping downstream of the discharge l
isolation valve l ;
I l
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
26 l
A variable-speed centrifugal pump is operating with the following parameters:
Speed
= 1,200 rpm Current
= 40 amperes Pump head
= 20 psi Pump flow rate = 400 gpm Which one of the following contains the approximate values of pump head and current if pump speed is increased to 1,600 rpm?
A.
25 psi, 55 amps B.
25 psi, 95 amps C.
36 psi, 55 amps D.
36 psi, 95 amps QUESTION:
27 1
The starting current in a typical ac induction motor is much higher than the full-load running current because:
A.
starting torque is much lower than running torque.
l B.
starting torque is much higher than running torque.
C.
rotor current during start is too low to generate significant counter electromotive force (CEMF) in the stator.
D.
rotor speed during start is too low to generate significant l
CEMF in the stator.
l i
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USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A l.-
QUESTION:
28 l
A main generator is operating in parallel with the power grid.
If the voltage supplied to the generator field is sicwly and continuously decreased, the generator will experience high current due to: (Assume no generator protective actuations occur.)
A.
excessive generator MWe.
l I
B.
excessive generator KVAR (VARs out).
C.
excessive generator KVAR (VARs in).
l D.
generator reverse power.
j 1
i QUESTION:
29 Which one of the following will provide motor protection against electrical damage caused by gradual bearing degradation?
A.
Undervoltage device B.
Underfrequency relay 1
C.
Overcurrent trip relay D.
Thermal overload device I
i l
- 1
1 USNRC CENERIC FUNDAMENTALS EXAMINATION i
APRIL 1997 BWR - FORM A QUESTION:
30 i
The number of starts for an electric motor in a given period of time should be limited because:
A.
overheating of the stator windings can occur due to high
{
starting currents.
B.
rotor damage can occur due to excessive cyclic stresses on the shaft.
I C.
overheating of the stator windings can occur due to shorting within the rotor.
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D.
rotor damage can occur due to excessive axial displacement of the shaft.
l 1
1
)
I 1
QUESTION: 31 1
Which one of the following.is the approximate condenser vacuum j
(inches Hg vacuum) when condenser pressure is 16 inches Hg i
absolute?
A.
4 inches Hg vacuum B.
8 inches Hg vacuum C.
12 inches Hg vacuum D.
14 inches Hg vacuum 1
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USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
32 i
Refer to the drawing of a lube oil heat exchanger (see figure below).
The lube oil heat exchanger is in service with the following i
inlet temperatures:
]
l Lube oil inlet 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 c,. )
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 I
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!!(bfiaciM COOUNG WATER 3 ::,,i i i 1 -
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e-l 3-
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- bb ht ?19 g %1wtw-1 1
LUBS OtL l
l LUBE O!L HEAT EXCHANGER 1
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USNRC CENERIC FUNDAMENTALS EXANINATION APRIL 1997 BWR - FORN A QUESTION:
33 During normal plant operation at 100% power, a main condenser develops an air leak that degrades vacuum at a rate of 1 inch Hg/ min.
Assuming the plant continues to operate at 100% power, condenser hotwell temperature will:
A.
increase because condensation of turbine exhaust steam is occurring at a higher temperature.
B.
increase because more work is being extracted from the steam by the turbine.
C.
decrease because condensation of turbine exhaust steam is occurring at a lower temperature.
D.
decrease because less work is being extracted from the steam by the turbine.
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l
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QUESTION:
34 Which one of the following will reduce the rate of heat transfer j
between two liquids in a heat exchanger? (Assume single-phase conditions and a constant specific heat for both liquids.)
[
A.
The inlet temperatures of both liquids are decreased by 20*F.
B.
The inlet temperatures of both liquids are increased by 20*F.
C.
The inlet temperature of the hotter liquid is increased by 20 F.
l, D.
The inlet temperature of the colder liquid is increased by 20 F.
l J l
_ -... =
UINRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
35 Refer to the drawing of a water cleanup system (see figure below).
All valves are identical and are initially 50% open.
To lower the temperature at point 4, the operator should adjust valve in the direction.
A.
A; open B.
B; shut C.
C; open D.
D; shut RETURN FROM SYSTEM SY EM <
1.
540*Fi'2 1
A 450*F HEAT EXCHANGER X
122*F C
250'F1!4 5
HEAT 90*F COOLING EXCHANGER D
6 WATER
--k<
l 110*F 122'F o 7 l
l ION EXCHANGER i
I WATER CLEANUP SYSTEM 0
1 24 -
a
_ a
_a m
-ak
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---A U NRC CENERIC FUNDAMENTALS EXAMINATION i
)
APRIL 1997 BWR - FORM A
\\
l QUESTION:
36 1
i Refer to the drawing of a lube oil heat exchanger (see figure l
below).
As tube fouling increases in the lube oil heat exchanger, cooling l
water outlet temperature will and lube oil outlet l
temperature will (Assume oil and cooling water flow rates do not change.)
A.
increase; decrease B.
increase; increase C.
decrease; increase i
D.
decrease; decrease j
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B,.
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- r*rL uy&=n..us a
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y COOUNO A
WATER gu
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4
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E'* T %.*T^
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I'$4sdENMd2p }3.,'."E41T?? $. "L..-
l':T*?.t$ s%:
ny-~
I
~~?rtm* 3 E d LUBE OtL LUBE OIL HEAT EXCHANGER l
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i USNRC @ENERIC FUNDAMENTALO EXAMINATION APRIL 1997 BWR - FORM A i
QUESTION:
37 l-The purpose of a demineralizer is to:
' A.
raise the conductivity of water without affecting pH.
l l
B.
reduce the conductivity of water without affecting pH.
l C.
increase the pH of water by reducing the number of positively l
charged ions in it.
D.
decrease the pH of water by increasing the number of negatively charged ions in it.
i i
i 1
i i
1 1
QUESTION:
38 Which one of the following will decrease the time required for a demineralizer to reduce the ionic impurities in a closed process p
water system?
l t
(
A.
Decrease the temperature of the process water from 110*F to 100 F l
l l
B.
Increase the flow rate of the process water from 95 gpm to 105 gpm l
C.
Divert 50% of the process water flow to bypass the demineralizer D.
Reverse the flow of process water through the demineralizer 4 l l
I
1 l
l l
USNRC CENERIC FUNDAMElf1ALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
39 l
A condensate demineralizer differential pressure ~(D/P) gauge indicates 4 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 increase in the accumulation of corrosion products in the demineralizer?
l CONDENSATE DEMINERALIZER FLOW D/P (PSID)
A.
100%
15.0 B.
75%
9.0 C.
60%
5.0 D.
25%
2.0 i
QUESTION:
40 Which one of the following is an unsafe practice if performed by an electrician working on or near energized electrical equipment?
A.
Having a person stand by to deenergize tb0 equipment in the event of an emergency B.
Using two hands for balance and to prevent dropping tools onto energized equipment C.
Standing on insulating rubber material to increase the electrical resistance of the body to ground D.
Covering exposed energized circuits with insulating material to prevent inadvertent contact l l
i USNRC Gk.12RIC FUNDANENTALS EXANINATION APRIL 1997 BWR - FORM A i
QUESTION:
41 Which one of the following results from a loss of control power to a breaker supplying a motor?
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 cpen due to the actuation of its protective trip device.
D.
Charging motor will not charge the close spring after the
. breaker trips open.
i
)
i i
QUESTION:
42 A main generator is being prepared for paralleling with the grid.
Which one of the following indicates that the nain generator and grid voltages are in phase?
A.
The voltage of the generator is equal to the voltage of the grid.
B.
The frequency of the generator is equal to the frequency of the grid.
C.
The synchroscope is turning slowly in the clockwise direction.
D.
The synchroscope is passing through the 12 o' clock position.
~
^
l USNRC @ENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
43 While remotely investigating the condition of a typical normally-j open motor control center (MCC) feeder breaker, an operator J
observes the following indications:
Green breaker position indicating light is lit.
Red breaker position indicating light is out.
MCC voltmeter indicates zero volts.
MCC ammeter indicates zero ampercs.
Based on these indications, the operator can accurately report that the breaker is open and racked to position.
A.
the OUT B.
the IN-j C.
the TEST D.
an unknown t
i 4.
USNRC CENERIC FUNDAMENTALS EXAMINATICN APRIL 1997 BWR - FORM A QUESTION:
44 Refer to the drawing of a valva control circuit (see figure below).
Which one of the following describes the purpose of the alarm in the control circuit shown in the accompanying drawing?
1 A.
Alert the operator when the valve motor circuit has been energized for 10 seconds after pushbutton PB2 is depressed
)
i B.
Alert the operator when the valve has not moved off its closed seat within 10 seconds of depressing pushbutton PB2 C.
Alert the operator that the valve is opening by sounding the alarm for 10 seconds after PB2 is depressed D.
Alert the operator if the valve has not reached full open within 10 seconds of depressing pushbutton PB2
+ 125 VDC l
VALVE P81 E82 POSITION (PUSH TO.
^T
[
R G
CLOSE
- 3 VALVE)
V AVE)
ACT _ _ CONTACT I'
(CLOSED i
l WHEN I
1 181 VALVE gg l
)
8 C
D) _
l
- ro a E---65eidx,
[C " - =-
l
-=
-m MOTOR OPEN VALVE.
(10 SEC (OPEN WHEN (OPEN CIRCUlf DEENERGlZE TWE DELAY VALVE FULLY WHEN TO CLOSE PICKUP)
CLOSED)
VALVE 125 VDC EN)
VALVE CONTROL CIRCUlT USNRC GENERIC FUNDAMENTALS EXANINATION APRIL 1997 BWR - FORN A QUESTION:
45 When comparing a delayed neutron and a prompt neutron, born from the same fission event, the prompt neutron is more likely to:
A.
cause fast fission of a U-238 nucleus.
)
B.
be captured by a U-238 nucleus at a resonant energy between 1 eV and 1000 eV.
C.
be captured by a Xe-135 nucleus.
D.
cause thermal fission of a U-235 nucleus.
i QUESTION:
46 Which one of the following will decrease the ability of the coolant to moderate neutrons in a reactor operating at saturated conditions?
A.
Decreasing moderator temperature B.
Decreasing feedwater inlet temperature C.
Decreasing reactor pressure vessel pressure D.
Increasing reactor recirculation system flow rate.
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
47 Which one of the following combinations of core conditions at 35%
4 power indicates the least amount of excess reactivity exists in the core?
CONTROL REACTOR RECIR-ROD POSITION CULATION FLOW.
A.
25% inserted 25%
B.
25% inserted 50%
C.
50% inserted 25%
D.
50% inserted 50%
QUESTION:
48 A reactor scrammed from 100% steady state power 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> ago due to an instrument malfunction.
All systems operated normally.
Given the following absolute values of reactivities added since the scram, assign a (+) or (-) as appropriate and choose the current value of core reactivity.
( ) 1.0% AK/K
=
Fuel temperature = ( ) 2.0% AK/K Control rods
( ) 14.0% AK/K
=
Voids
'( ) 3.0% AK/K
=
-A.
-8.0% AK/K B.
-10.0% AK/K C.
-14.0% AK/K D.
-20.0% AK/K._
__-_-.__m l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
49 A subcritical reactor has an initial K rr of 0.8 at a source range e
count rate of 100 cps.
Positive reactivity is added until K,cc equals 0.95.
What will be the final equilibrium source range count rate?
A.
150 cps l
B.
200 cps C.
300 cps l
i j
D.
400 cps l
i l
l QUESTION:
50 l
After the first fuel cycle, subcritical multiplication can produce a visible neutron level indication on the source range nuclear instrumentation following a reactor shutdown without
(
installed neutron sources.
This is because a sufficient source of neutrons is being produced by:
A.
spontaneous neutron emission from control rods.
l B.
photo-neutron reactions in the moderator.
l C.
low level thermal fission in the fuel.
I j
D.
alpha-neutron reactions in the fuel.
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
51 A reactor is critical at 10-5% power with a xenon-free core.
The operator continuously withdraws control rods until a 60-second reactor period is reached and then stops control rod motion.
Upon stopping rod withdrawal, reactor period will immediately:
A.
stabilize at 60 seconds until power reaches the point of adding heat.(POAH).
B.
lengthen and then stabilize at a value greater than 60 seconds until power reaches the POAH.
C.
shorten and then slowly and continuously lengthen until power reaches the POAH.
D.
lengthen and then slowly and continuously shorten until power reaches the POAH.
l l
QUESTION:
52 Which one of the following contains the nuclides responsible for
{
l I
most of the resonance capture of fission neutrons in the core at the beginning of the sixth fuel cycle?
(Assume that each refueling replaces one-third of the fuel.)
L A.
U-238 and Pu-240 D.
}
x
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1957 BWR - FORM A QUESTION:
53 Which one of the following describes why most reactor power is produced in the lower half of a core (versus the upper half) that has been operating at 100% power for several. weeks at the beginning of a fuel cycle?
A.
Xenon concentration is higher in the upper half of the core.
B.
The moderator-to-fuel ratio is higher in the upper half of the core.
C.
The void coefficient is adding more negative reactivity in the upper half of the core.
D.
Control rods are adding more negative reactivity in the upper half of the core.
1 l
l I
i i
QUESTION:
54 7
l l
A reactor is critical at the point of adding heat during a i
l reactor startup.
Reactor pressure is stable at 600 psig and main l
steam isolation valves are open.
Then, control rods are manually l
withdrawn for 5 seconds.
Assuming the reactor does not scram, when conditions stabilize, reactor power will be and reactor vessel temperature i
l will be 1
A.
the same; the same B.
the same; higher C.
higher; the same l
D.
higher; higher l
I l
l l 1
~.
Uf,NRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORN A QUESTION:
55 A reactor has been shut down for three weeks with all control rods fully inserted.
If a center control rod is fully and continuously withdrawn from the core, neutron population will:
(Assume the reactor remains subcritical.)
A.
increase and stabilize above the original level.
B.
increase, then decrease and stabilize at the original level.
C.
increase, then decrease and stabilize above the original level.
D.
remain the same during and after the withdrawal.
l 1
QUESTION:
56 l
How is control rod density affected as control rods are inserted during a reactor shutdown?
A.
Increases continuously during rod insertion B.
Decreases continuously during rod insertion C.
Increases initially, then decreases after 50% of the rods are inserted D.
Decreases initially, then increases after 50% of the rods are inserted -
(
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
57 A control rod is positioned in a reactor with the following neutron flux parameters:
Core average thermal neutron flux
= 1 x 10" n/cm -sec 2
Control rod tip thermal neutron flux = 5 x 10" n/cm -sec 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 _
2 l
sec, then the differential control rod worth will increase by a factor of (Assume the core average thermal neutron flux is' constant.)
(-
A.
0.5 B.
1.4 C.
2.0 D.
4.0 QUESTION:
58 A reactor had been operating at 50% power for two weeks when power was increased to 100% over a 3-hour period.
To maintain reactor power stable during the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, which one of the
{
following incremental control rod manipulations will be required?
A.
Withdraw rods slowly during the entire period B.
Withdraw rods slowly at first, then insert rods slowly i
C.
Insert rods slowly during the entire period i
D.
Insert rods slowly at first, then withdraw rods slowly USNRC GENERIC FUNDANENTALS EXANINATION APRIL 1997 BWR - FORN A QUESTION:
59 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.
l l
l QUESTION:
60 l
l A reactor has been operating at 100% power for eight weeks when a reactor scram occurs.
The reactor is critical 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> later and power is increased to 100% over the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
How is core Xe-135 concentration behaving when power reaches 100%?
A.
Xe-135 is building in toward equilibrium.
l l
B.
Xe-135 is burning out toward equilibrium.
C.
Xe-135 is building in toward a peak value.
D.
Xe-135 is burning out toward a minimum value.
4 1
4 4 r
. ~. - - _
l USNRC EENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
61 Which one of the following lists the proper order of substances from the largest to the smallest microscopic cross sections for absorption of thermal neutrons?
A.
Gadolinium, U-235, Xe-135, U-238 B.
Gadolinium, Xe-135, U-235, U-238 C.
Xe-135, U-235, gadolinium, U-238 D.
Xe-135, gadolinium, U-235, U-238 j
QUESTION:
62 The primary method of xenon-135 production during reactor i
operation at steady state full power is by and the primary method of samarium-149 production is by A.
fission of U-235; fission of U-235 i
B.
fission of U-235; decay of Pm-149 C.
decay of I-135; fission of U-235 i
D.
decay of I-135; decay of Pm-149 l
l f
I 1
(
l I
( i I
USNRC EENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
63 L
i A reactor has been operating at 100% power for two weeks when I
power is decreased to 10% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Immediately following the power decrease, core xenon-135 concentration will for a period of A.
increase; 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B.
increase; 8 to 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> C.
decrease; 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> D.
decrease; 8 to 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> l
QUESTION:
64 Refer to the drawing of K rr versus core age (see figure below).
e The decrease in K.re from point 1 to point 2 is primarily caused by:
l A.
depletion of fuel.
~
B.
burnout of burnable poisons.
C.
initial heat-up of the' reactor.
D.
buildup of fission product poisons.
3 K,g 1
l 2
4 Core Age I
K,gVERSUS CORE AGE f !
USNRC @ENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A j
QUESTION:
65 i
A reactor startup is in progress with the reactor currently l
subcritical.
t Which one of the following describes the change in count rate resulting.from a short control rod withdrawal with Krr at 0.99 as compared to an identical control rod withdrawal with K.,, at 0.95?
(Assume reactivity additions are equal, and the reactor remains subcritical.)
I A.
Both the prompt jump in count rate and the increase in stable count rate will be the same.
B.
Both the prompt jump in count rate and the increase in stable count rate will be smaller with K.cr at 0.95.
i
~
C.
The prompt jump in count rate will be smaller with K.tc at 1
0.95, but the increase in stable count rate will be the same.
D.
The prompt jump in count rate will be the same, but the increase in stable count rate will be smaller with Kerr at i
0.95.
QUESTION:
66 A reactor is operating at 80% power near the end of a fuel cycle.
Which one of the following lists the typical method (s) used to add positive reactivity during a normal power increase to 100%?
A.
Withdrawal of deep control rods and increasing recirculation flow rate B.
Withdrawal of deep control rods only C.
Withdrawal of shallow control rods and increasing recirculation flow rate D.
Withdrawal of shallow control rods only I
^
) '
L
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
67 During a reactor startup, the first reactivity addition caused the count rate to increase from 20 to 40 cps.
The second reactivity addition caused the count rate to increase from 40 to 80 cps.
Assume ker was 0.92 prior to the first reactivity e
addition.
Which one of the following statements describes the magnitude of the reactivity additions?
A.
The first reactivity addition was approximately twice as large as the second.
B.
The second reactivity addition was approximately twice as large as the first.
C.
The first and second reactivity additions were approximately the same.
D.
.There is not enough data given to determine the relationship
.between raactivity values.
i j
l QUESTION:
68 l
A reactor startup is in progress following a one-month shutdown.
Upon reaching criticality, the operator establishes a positive l
80-second period and stops rod motion.
I l
- After an additional 30 seconds, reactor power will be and reactor period will be (Assume reactor power remains below the point of adding heat.)
l l~
A.
increasing; increasing i
B.
increasing; constant C.
constant; increasing i
D.
constant; constant 1
3
+
- ~. ~ -.
?
~U NRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1997 BWR - FORM A QUESTION:
'6 9 -
4 A reactor is. critical at the point of adding heat when a small I
amount of negative reactivity is added to the core.
If the same amount of positive reactivity is added to the core approximately l
5 minutes later, reactor ~ power will:
l A.
stabilize at the subcritical multiplication equilibrium neutron level.
l B.
stabilize at a level lower'than the initial power level.
l C.
continue to decrease on a negative 80 second period.
l D '.
stabilize at the initial power level.
QUESTION:
70 i
When a reactor is exactly critical, reactivity is:
A.
greater than 1.0 AK/K.
B.
equal to 1.0 AK/K.
l l
C.
less than 1.0 AK/K.
D.
undefined.
l 4
i l l l
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
71 After taking critical data during a reactor startup, the operator establishes a 38-second reactor period to increase power to the point of adding heat (POAH).
Which one of the following is the approximate amount of negative reactivity required.to stop the power increase at the POAH?
(Assume-average S = 0.00579)
A.
-0.01% oK/K B.
-0.12% AK/K C.
-0.16% oK/K D.
-0.21% oK/K QUESTION:
72 A reactor is initially operating at 100% power when a control rod fully inserts into the core.
Assuming no operator action and no reactor scram, reactor power will initially decrease and then:
A.
stabilize at a lower power level with the void boundary higher in the core.
B.
stabilize at a lower power level with the void boundary lower in the core.
C.
return to the original power level with the void boundary higher in the core.
D.
return to the original power level with the void boundary lower in the core.
1 _
,c_~
USNRC CENERIC FUNDAMENTALS ETRAMINATION APRIL 1997 BWR - FORM A l
QUESTION:
73 A water storage tank is enclo' sed'to prevent vapors from escaping to the environment.
The tank is also pressurized with nitrogen to prevent air inleakage.
A differential pressure detector with a dry reference leg is used to measure the tank level.
To achieve the greatest accuracy of measurement, the low pressure side of the detector should sense which one of the following?
A.
The pressure at the bottom of the tank B.
The pressure of the atmosphere surrounding the tank l
C.
The pressure of a column of water external to the tank D.
The pressure of the gas space at the top of the tank l
1 l
' l QUESTION:
74 Consider a saturated vapor at 470 F.
If the pressure of the vapor remains constant and heat is added, vapor temperature will and vapor quality will A.
remain the same;' remain the same B.
remain the same; increase i
C.
increase; remain the same D.
increase; increase l
l l
I.
USNRC CENERIC FUNDAMENTALS EXAMINATION l
APRIL 1997 BWR - FORM A QUESTION:
75 Which one of thd following sets of water parameters will result in the highest fluid quality?
A.
500*F; 1100 Btu /lbm B.
320*F; 1070 Btu /lbm C.
200*F; 1040 Btu /lbm D.
160*F; 960 Btu /lbm e
l l
l QUESTION:
76 i
A plant is operating at 80% power with 5*F of condensate depression in the main condenser.
If the condensate depression increases to 10*F, plant efficiency will and the probability of condensate pump cavitation will A.
increase; increase
. B.
increase; decrease 3
i C.
decrease; increase l
i D.
decrease; decrease
[
l
. - ~. - -. - -.. -
E USNRC CENERIC FUNDANT.NTALS EXAMINATION i
APRIL 1997 BilR - FORM A l
\\
l I
QUESTION:
77 1
Refer to the drawing of an operating steam-jet air ejector (see
)
figure below).
At which one of the following locations is the lowest pressure experienced?
l A.
1 i
B.
2 1
l' C.
3 D.
4 1 2 3
4 l
l l I
lii !f, k MO'df l
I}$
p:sCHARGE l
sitAM"N' 4 e__ sitAM a
we y
bf o
u Aid & STEAM STEAM JET AIR EJECTOR l
i 4
I l -
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
78 If superheating-of'the.i'nlet steam t'o the low pressure turbines is reduced, low pressure turbine work output will and low prescure turbine exhaust steam moisture content will A.
increase; increase B.
increase; decrease C.
decrease; increase D.
decrease; decrease QUESTION:
79 Refer to the drawing of four centrifugal pump operating curves (see figure below).
A centrifugal pump is operating in a cooling water system.
Another identical centrifugal pump is started in series with the i
first.
Which set of curves illustrates the resulting change in i
system parameters?-
A.
1.
B.
2.
C.
3.
D.
4.
l PUMP PUMP HEAD HEAD i
FLOW FLOW EE j
I PUMP PUMP HEAD HEAD FLOW FLOW M
51 CENTRlFUGAL PUMP OPERATING CURVES l
1 I
- l..
UINRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A i
QUESTION:
80 I
. l
- Which one of the f611owing components of,a centrifuga_1 pump has the specific primary' function of converting the kinetic energy of l
a fluid into pressure?
I 1
A.
Volute i
B.
Impeller C.
Pump shaft D.
Discharge nozzle QUESTION:
81 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 their 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 pump overheating caused by low flow B.
LPCI pumps to avoid motor overheating caused by low flow C.
HPCI pumps to avoid pump overheating caused by high flow i
D.
HPCI pumps to avoid motor overheating caused by high flow t
UCNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
82 Refer to the drawing of a fuel rod and c..oolant 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 r% ~.:
CLAD l
rust cettrrr r%
i ss i
r%
l i
COOLANT COOLANT FLOW FLOW
%s FUEL ROD AND COOLANT FLOW CHANNEL l
r..
USNRC @ENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
83 The-powe,r,rangbnoclearinstrumentshavebeenadjustedto100%
~
based on a calcnlated heat balance.
Which one of the following will result in indicated reactor power being lower than actual reactor power?
1 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 pressure, i
i l
l QUESTION:
84 Which one of the following pairs of fluids undergoing heat l
transfer in identical heat exchangers will yield the greatest i
heat exchanger overall heat transfer coefficient?
j A.
Oil to water B.
Air to water C.
Steam to water j
1 1
D.
Water to water 1
)
r
l USNRC GENERIC FUNDANENTALS EXANINATION I
APRIL 1997 BWR - FORN A l
QUESTION:
85 Refer to the' drawing of a pool boiling curve-(see figure below).
i l
l Which one of the following describes the conditions in a fuel channel that is experiencing region III heat transfer?
i A.
Complete steam blanketing of the fuel rod surface l
B.
Alternate wetting and drying of the fuel rod surface l
C.
Saturated nucleate boiling I
D.
Subcooled nucleate boiling l
l ll 111 IV I
LOG i
HEAT FLUX
)
i l
/
LOG AT POOL BOILING CURVE I
I 1 -.
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR
- FORM A QUESTION:
86' During full power operation, critical heat flux is most likely to occur in a/an:
A.
center fuel bundle with flow restrictions.
B.
center fuel bundle withobt flow restrictions.
C.
outer fuel-bundle with flow restrictions.
D.
outer fuel bundle without flow restrictions.
l l
1 l
QUESTION:
87 Reactor A and reactor B are currently operating at 50% power with a normal neutron flux distribution in each core.
The reactors are identical except that reactor A has core orifices and reactor l
B does not.
Each reactor has the same core mass flow rate.
i Reactor B will have the critical power and the core differential pressure.
A.
higher; higher B.
higher; lower l-C.
lower; higher i
D.
lower; lower 1l 1
a 1 4
i t
. -... - -. -.. =..
l l
U?.NRC GENERIC FUNDAMENTALS EXAMINATION l
APRIL 1997 BWR - FORM A l
QUESTION:
88.
j Refer to t'he drawing of a pool boiling curve (see figure below).
]
In which region (s) of the curve does the reactor normally operate l
to transfer heat from the fuel clad to the coolant at 100% power?
I i
l A.
Regions II and III i
l B.
Region II only C.
Regions I and II l
D.
Region I only 9
l ll lil IV LOG HMT FLUX j
2 LOGAT l
POOL BOluNG CURVE l
l 1 __
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
89 A reactor is operating at 100% power.
Recirculation flow is decreased from 100% to 80%.
Which one of the following statements describes the initial response of the boiling boundary within the core?
A.
It physically moves down the fuel rods, because more Btus per pound mass of water are now being transferred.
B.
It physically moves down the fuel rods, because fewer Btus per pound mass of water are now being transferred.
C.
It physically-moves up the fuel rods, because more Btus per pound mass of water are now being transferred.
D.
It physically moves up the fuel rods, because fewer Btus per pound mass of water are now being transferred.
QUESTION:
90 A reactor is operating at steady state 90% power.
Which one of the following will cause the two-phase coolant flowing upward in a fuel channel to become closer to the onset of transition boiling?
(Assume reactor power does not change unless stated.)
A.
Reactor pressure increases.
B.
Recirculation flow increases.
C.
Feedwater temperature decreases.
D.
Associated bundle power decreases.
I-USNRC EENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A I
l QUESTION:
91 l
Refer to the drawing of a fuel rod and coolant flow channel at l
the beginning of core life (see figure below).
At 100% reactor power, the greatest temperature difference in a fuel channel radial temperature profile will occur across the:
A.
fuel centerline to fuel pellet surface.
B.
fuel-to-clad gap.
C.
zircaloy cladding.
D.
flow channel boundary (laminar) layer.
F%
CLAD j -
rueL eetter w
I 1
ms r%
COOLANT COOLANT FLOW FLOW
%s II FUEL ROD AND COOLANT FLOW CHANNEL I..
-. - ~
Uf.NRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
92 i
Which one of the following describes the fuel-to-coolant thermal i
conductivity for a fuel assembly at the beginning of core life (BOL) as compared to the end of core life (EOL)?
A.
Larger at BOL due to a higher fuel pellet density B.
Larger at BOL due to lower contamination of fuel rod fill gas with fission product gases C.
Smaller at BOL due to a larger gap between the fuel pellets and clad i
D.
Smaller at BOL due to a smaller corrosion film on the surface of the fuel rods i
1 QUESTION:
93 l
l l
A step increase in reactor power results in a fuel rod surface temperature increase from 555*F to 585*F at steady state conditions.
The fuel thermal time constant is 6 seconds, l
Which one of the following is the approximate fuel rod surface temperature 6 seconds after the power change?
l A.
574*F l
B.
570*F C.
567*F
[
D.
563*F I I
l USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
94 Which one of the following describes the basis for the 2200*F maximum fuel clad temperature limit?
A.
The material strength of zircalcy decreases rapidly at i
. temperatures above 2200 F B.
At the normal operating pressure of the reactor vessel a clad temperature of 2200"F indicates that the critical power has been exceeded.
C.
The race of the zircaloy-steam reaction becomes significant at temperatures above 2200*F.
D.
2200 F is approximately 500*F below the fuel clad melting j
temperature.
1 QUESTION:
95 Which one of the following is most likely to result in fuel failure due to pellet-clad interaction?
A.
Increasing reacter power from 20% to 50% near the beginning of a fuel cycle B.
Increasing reactor power from 20% to 50% near the end of a fuel cycle C.
Increasing reactor power from 70% to 100% near the beginning of a fuel cycle D.
Increasing reactor power from 70% to 100% near the end of a fuel cycle l
l USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A l
QUESTION:
96 L
Which one of the following is responsible for the fuel clad failure caused by operating the reactor above the limit for linear heat generation rate (LHGR)?
l l
l A.
Fission product gas expansion causes clad internal design pressure to be exceeded.
B.
Corrosion buildup on the fuel clad surface reduces heat transfer and promotes transition boiling.
C.
The zircaloy-steam reaction causes accelerated oxidation of the clad at high temperatures.
D.
The difference between thermal expansion rates of the fuel pellets and the clad causes severe clad stress.
QUESTION:
97 Which one of the following is indicated when the maximum average power ratio (MAPRAT) is less than 1.0?
A.
The linear heat generation rate (LHGR) limit has been exceeded.
B.
The average planar linear heat generation rate (APLHGR) limit has been exceeded.
C.
The APLHGR limit has not been exceeded.
1 D.
The LHGR limit has not been exceeded.
i l
i USNRC EENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A QUESTION:
98 t
A plant is operating at 60% reactor power.
Which one of the following will result in the highest critical power ratio?
l (Assume neutron flux distribution does not change.)
A.
25% power increase using only recirculation flow i
i B.
25% power increase using only control rods C.
25% power decrease using only recirculation flow l
D.
25% power decrease using only control rods l
I C
QUESTION:
99 Brittle fracture of the reactor vessel (RV) is least likely to occur during a of the RV when RV temperature is the reference temperature for nil-ductility transition (RTu:n).
A.
cooldown; above B.
heatup; above 1
C.
cooldown; below D.
heatup; below I
i I
USNRC @ENERIC FUNDAMENTALS EXAMINATION APRIL 1997 BWR - FORM A i
QUESTION:
100 f
Two identical reactors have been in operation for the last 10 years.
Reactor A has experienced 30 heatup/cooldown cycles with an average power capacity of 60%.
Reactor B has experienced 40 heatup/cooldown cycles with an average power capacity of 50%.
Which reactor will have the lowest reactor vessel nil-ductility transition temperature?
A.
Reactor A due to the higher average power capacity B.
Reactor A due to the fewer number of heatup/cooldown cycles C.
Reactor B due to the lower average power capacity l
D.
Reactor B due to the greater number of heatup/cooldown cycles l
i I
l l
i i
I t l i
UNITED STATES NUCLEAR REGULATORY COMMISSION PRESSURIEED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 - FORM A Please Print Name:
Facility:
Docket No.:
Start Time:
Stop Time:
INSTRUCTIONS TO CANDIDATE 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 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 All work done on this examination is my own.
I have neither given nor received aid.
Applicant's Signature RULES AND GUIDELINES FOR THE GENERIC FUNDAMENTALS 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.
l 1.
Print your name in the blank provided on the cover sheet of the examination.
2.
Fill in the name of your facility.
3.
Fill in your individual docket number.
4.
Fill in your start and stop times at the appropriate time.
1 5.
Two aids are provided for your use during the examination.
3 (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 ONE examinee may leave the room at a time.
In order to avoid the appearance or possibility of cheating, avoid all contact with anyone outside of the examination room.
- 10. Af ter 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. 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.
{
- 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 FUNDAMaqTAks EXAMINATION EQUATIONS AND CONVERSIONS HANDOUT SHEET EOUATIONS dic A T P = P 108*"
=
o p
P = P e "
o Q = dtAh A = A,e-^t Q= UAAT CRsfo = S/ (1 - K rr) e 3
nat cir CR (1 - K.trt) = CR (1 - K rr2) 1 2
e 2
AT " $nat cire 1/M = CR /CRx 1
2 K.tr = 1/(1 - p)
DRW = $t pj 9 vg p=
(K,cc - 1)/Ker F = PA e
SUR = 26.06/t g = pg9 b-P
$ ump = dtAPU 1 =
P g
S eff E = IR g
g p=+
T 1+A T
Eff. = Net Work Out/ Energy In eff (W-Y) + g (z2 - Z)
(* = 1 x 10-' seconds U( 2 -P) +
= 0 1
i 2g ge A,g e = 0.1 seconds-2 32.2 lbm-ft/lbf-sec2 ge
=
CONVERSIONS 3.41 x 10' Btu /hr 1 Curie 1 Mw 3.7 x 102 dps
=
=
2.54 x 103 Btu /hr 1 kg 1 hp 2.21 lbm
=
=
1 Btu =
778 ft-lbf 1 gal t,
8.35 lbm
=
- C (5/9) ('F - 32) 1 f t. tor 8
7.48 gal
=
=
(9 /5) ( *C) + 32 F
=
l B
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORN A QUESTION:
1 1
Refer to the drawing of a typical safety valve (see figure below).
The component indicated by the solid arrow is used by the operator to manually:
1 A.
ratchet open the safety valve.
B.
pop open the safety valve.
C.
gag shut the safety valve.
D.
determine the position of the safety valve.
mw
-(TTL )
r\\
iTp E
s lI II
@h\\\\
\\k\\N 5-
-M,J s
f c>
EVE g a Oh h F
SAFETY VALVE i
4_
USNRC GEIGRIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
2 Which one of the following statements describes the flow rate characteristics of a typical gate valve in an operating water system?
A.
The first 25% of valve disk travel in the open direction 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 change in flow rate as the last 25% of valve disk travel.
D.
A gate valve that has been opened to 25% of valve disk travel will result in approximately 25% of full flow rate.
QUESTION:
3 Which one of the following is not a generally accepted method for locally verifying that a manual valve is fully open?
A.
Observe local flow rate instrumentation.
B.
Check that the local valve position indicator indicates "open."
C.
Turn the valve handwheel in the "close" direction and verify that some movement occurs, then fully open the valve.
D.
Turn the valve handwheel in the "open" direction and verify that no movement occurs..
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
4 Refer to the drawing of a spring-loaded air-operated valve shown in a throttled position (see figure below).
Which one of the following will be the valve position following a reduction in air pressure to the valve actuator caused by a leaking air connection at the valve?
A.
Original position B.
More closed C.
More open D.
Varies with system flow FAILS TO VENT P_OSITION O
6 c3 AIR SUPPLY k
- L I k N
l l VENT
,1 E, SPRING-LOADED AIR. OPERATED VALVE
( -
USNRC GENERIC FUNDABENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
5 A steam flow measuring instrument uses density compensation and square root compensation to convert the differential pressure (D/P) across the flow element to lbm/hr.
The purpose of square root compensation in this flow measuring instrument is to convert to A.
volumetric flow rate; mass flow rate B.
volumetric flow rate; D/P C.
D/P; mass flow rate D.
D/P; volumetric flow rate 1
i
(
i QUESTION:
6 Many steam generator water-level instruments are designed with a condensing chamber in the reference leg.
The purpose of the condensing chamber is to:
A.
maintain a constant water level in the reference leg during normal operations.
B.
provide pressure compensation for the steam pressure exerted on the variable leg.
C.
prevent reference leg flashing during a rapid depressurization of the steam generator.
D.
ensure the reference leg temperature remains close to the temperature of the variable leg.
....-...~
l USNRC @XNERIC FUNDAMENTALS EXAMINATION l
APRIL 1997 PWR - FORM A QUESTION:
7 l
Refer to the drawing of a pipe elbow used for flow measurement'in a cooling water system (see figure below).
A differential pressure (D/P) flow detector is connected to 1
instrument lines A and B.
1 If instrument line B develops a leak, indicated flow rate will 1
i due to a measured D/P.
j A.
increase; larger B.
increase; smaller C.
decrease; larger D.
decrease; smaller j
l iit 1
1 A
i
[
FLOW
{
b B
PIPE ELBOW. TOP VIEW l
l 1
1 _
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
8 Refer'to the drawing of a water storage tank with two differential pressure (D/P) level indicators (see figure below).
Indicator 1 was calibrated at 180*F and indicator 2 was calibrated at l'20*F.
If current tank water temperature is 150 F, then indicator:
A.
1 will read greater than indicator 2 and greater than actual level.
B.
1 will read greater than indicator 2 and less than actual level.
C.
2 will read greater than indicator 1 and greater than actual level.
D.
2 will read greater than indicator 1 and less than actual level.
L i
70 AT RE V
/ /
WATER
/
e-
+
TANK DIFFERENTIAL PRESSURE LEVEL INDICATORS
_ 9_
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
9 A centrifugal pump is taking suction from the bottom of a vented cylindrical storage tank that contains 100,000 gallons of water at 60*F.
A pressure gauge at the inlet to the pump indicates 40 psig.
Over the next several days storage tank temperature increases to 90*F with no change in tank water level and no change in head loss in the pump suction line.
Which one of the following is the current approximate pressure at the inlet to the pump?
A.
39.8 psig B.
37.4 psig C.
34.6 psig D.
31.2 psig QUESTION:
10 l
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 l
producing a system pressure indication of 75 psia, l
l If the detector diaphragm ruptures, indicated pressure will be approximately:
A.
100 psia.
1 B,
60 psia.
C.
15 psia.
D.
O psia.
3 4.
l' l
USNRC EENERIC FUNDAMENTALS EXAMINATION l
APRIL 1997 PNR - FORM A QUESTION:
11 In contrast to a thermocouple, a resistance temperature detector:
A.
is used in high temperature applications.
B.
does not require an external power supply for temperature indication.
C, uses a single type of metal in the sensing element.
D.
is commonly placed in direct contact with the monitored substance.
QUESTION:
12 A reactor is shut down at 100 cps in the source /startup range when a loss of coolant accident occurs.
Which one of the following describes excore source /startup range neutron level indication as homogeneous core voiding increases from 20% to 40%?
i A.
Decreases because Kerr is decreasing l
B.
Increases because K rr is increasing e
C.
Decreases because less neutron leakage is occurring D.
Increases because more neutron leakage is occurring
{
1 l
\\
l )
1
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
13 Which one of the following types of radiation will produce the greatest. number of ions while passing through 1 centimeter of air?
(Assume the same kinetic energy for each.)
A.
Alpha B.
Beta C.
Gamma D.
Neutron l
QUESTION:
14 Which one of the following will cause an upscale failure of a boron-trifluoride (BF ) failed fuel detector operating in the 3
proportional region?
A.
The detector electrode high voltage power supply output has decreased 5% due to setpoint drift.
B, The detector chamber has become flooded with water due to leakage around the electrodes.
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.
l-t USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
15 An automatic flow controller is being used to position a valve in a cooling water system.
A signal from the valve, which is
~ proportional to valve position, is returned to the controller.
This signal is referred to as:
A.
~ gain.
B.
bias.
C.
feedback.
D.
error.
QUESTION:
16
.Jul air-operated isolation valve requires 3,200 pounds-force from its pneumatic actuator and 4 inches of stem travel for proper l
operation.
The area of the actuator diaphragm is 160 square inches.
l What is the minimum air pressure (rounded to the nearest psig) required for proper valve operation?
I A.
20 psig B.
40'psig C.
60 psig D.
80 psig i
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
17 Refer to the drawing of a pneumatic control system (see figure below).
An increasing steam generator (S/G) level will decrease the S/G I
level control signal and reduce the control air pressure applied to the feed control valve which reduces feedwater flow to the S/G.
If the level control signal fails high, S/G level will because the control air pressure to the valve positioner will 1
A.
increase; increase B.
increase; decrease C.
decrease; increase D.
' decrease; decrease I
i 4/P CONVERTER PROM FRM PROTECTION i
LE LOGIC i
CONTROL.
J VALVE y w POSITIONER l
i
-4 h "
1 P" ATMOSPHERE l
j
'FC AIR SUPPLY FROM TO FEED STEAM PUMPS FEED GENERATOR C TROL A sen******ese LOGIC 880N AL = === =
C TROL VALVE 1
i l
PNEUMATIC CONTROL SYSTEM PWR i
4 1
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
18 A diesel generator is supplying a bus with the governor operating in the isochronous mode.
If a large electrical load is started on the generator bus, generator frequency will:
A.
remain constant during and after the load start.
B.
initially decrease, then increase and stabilize above the initial value.
C.
initially decrease, then increase and stabilize below the initial value.
D.
initially decrease, then increase and stabilize at the initial value.
QUESTION:
19 The level in a tank is being controlled by an automatic level controller and is initially at the controller setpoint.
A drain valve is then opened, causing tank level to begin to decrease.
The decreasing level causes the controller to begin to open a makeup supply valve.
After a few minutes, a new, steady-state tank level below the original level is established, with the supply rate equal to the drain rate.
l l
The controller in this system uses control.
A.
integral (reset) plus derivative (rate)
B.
proportional plus integral (reset)
C.
proportional D.
bistable UZNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
20 Starting a centrifugal pump with the discharge valve throttled (versus fully open)-
the possibility of pump runout and the possibility of pump cavitation.
A.
increases; decreases B.
increases; increases C.
decreases; decreases D.
decreases; increases l
l QUESTION:
21 l
A plant !.s operating at full power when a 200 gpm reactor coolant leak occars, which results in a reactor scram and initiation of emergency coolant injection.
Reactor coolant system pressure stabilizes at 1000 psia and all injection pumps are operating with i
l their pump recirculation lines isolated.
The shutoff heads for j
the pumps are as follows:
l High pressure injection (HPI) pumps:
2500 psia t
Low pressure injection (LPI) pumps:
200 psia l
l Which pumps must be stopped quickly and why?
A.
HPI pumps to prevent motor overheating caused by high flow B.
HPI pumps to prevent pump overheating caused by low flow C.
LPI pumps to prevent motor overheating caused by high flow D.
LPI pumps to prevent pump overheating caused by low flow USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A i
i QUESTION:
22 A centrifugal pump is. operating at rated conditions in an open.
f system with all valves fully open.
If the pump suction valve is throttled to 50% closed, pump discharge pressure will and pump differential pressure will A.
remain the same; remain the same l
B.
. decrease; remain the same C.
remain the same; decrease D.
decrease; decrease b
QUESTION:
23 A centrifugal pump is operating at rated conditions in an open system with all valves fully open.
If the pump discharge valve is throttled to 50% closed, pump discharge pressure will and pump motor current will A.
decrease; decrease i
B.
decrease; increase C.
increase;' increase D.
increase; decrease j
i...
= - -.
s USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
24 Refer to the drawing of a cooling water system (see figure below).
The centrifugal pump is circulating water at 180*F with a motor current of 200 amps.
After several hours system temperature has decreased such that the water density has increased by 3%.
Assuming pump head and volumetric flow rate do not change, which one of the following is the new pump motor current?
A.
194 amps i
B.
197 amps C.
203 amps I
D.
206 amps P
Ti"a" HEAT EXCHANGER r
HE LOADS A ER I
to"mo's l
PUMP A i
COOLING WATER SYSTEM l
i
.. _ - _ ~. -. _ -
- - ~ _.
i USNRC~CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
25 A motor-driven centrifugal pump is operating in an open system with its discharge valve throttled to 50%.
If the discharge valve is fully opened, available net positive suction head (NPSH) will and required NPSH will A.
remains the same; increase B.
remains the same; remains the same C.
decrease; increase D.
decrease; remains the same QUESTION:
26 A variable-speed positive displacement pump is operating at 100 rpm with a flow rate of 60 gpm in an open system.
To decrease pump flow rate to 25 gpm, pump speed must be decreased to approximately:
A.
17 rpm.
B.
33 rpm.
C.
42 rpm.
D.
64 rpm.
]
i 1 l
USNRC GENERIC-FUNDADENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
27 A cooling water pump is being driven by an ac induction motor.
Which one of the following describes how and why pump motor current will change if the pump shaft seizes?
A.
Decreases due to decreased pump flow B.
Decreases due-to increased counter electromotive force C.
Increases due to decreased pump flow D.
Increases due to decreased counter electromotive force l
l QUESTION:
28 Which one of the following will provide motor protection against electrical damage caused by gradual bearing degradation?
A.
Thermal overload device B.
Overcurrent trip relay C.
Underfrequency relay D.
Undervoltage device i
-. -... ~..... ~
USNRC @ENERIC FUNDAMENTALS EXAMINATION
' APRIL 1997 PNR - FORM A QUESTION:
29 A main generator is operating on the grid with the following indications:
l 600 MWe
)
100 MVAR (VARs in) 13,800 amps 25,000 volts If main generator excitation is increased slightly, amps will and MWe will I
A.
decrease; increase I
B.
increase; increase 1
C.
decrease; remain the same D.
increase; remain the same QUESTION:
30 A centrifugal pump is operating at 600 rpm with the following parameters:
Motor current 100 amperes
=
Pump head 50 psid
=
Pump flow rate = 880 gpm Which one of the following will be the approximate value of pump head if pump speed is increased to 1200 rpm?
A.
71 psid B.
126 psid C.
172 psid D.
200 psid W
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
31 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.)
A.
Current immediately increases to the full-load value and then gradually decreases to the no-load value.
B.
Current 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 no-load value after several seconds and then stabilizes.
D.
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.
l l
f f
i-USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
32 Refer to the drawing of a water cleanup system (see figure below).
Valves A, B,
and C are fully open.
Valve D is 80% open.
All temperatures are as shown.
If valve D is then throttled to 50%, the temperature at point:
j 3 will decrease.
B.
4 will 4.ncrease.
4 C.
5 w1 _.ncrease.
D.
6 411' decrease.
i R
RN FROM SYSTEM SYSTEM t
l n
540*FI'2 1
A X
HEAT EXCHANGER 122*F C
250*F1l4
~
5 i
COOUNG EXCHANGER 6
WATER 110*F 122'Fo7 ION EXCHANGER
)
l WATER CLEANUP SYSTEM l
l UZNRC CENERIC FUNDAMENTALS EXAMINATICN APRIL 1997 PWR - FORM A QUESTION:
33 Refer to the drawing of a lube oil heat exchanger (see figure below).
The lube oil heat exchanger is placed in service with the following inlet temperatures:
Lube oil inlet 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 c. )
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 Mika G T.& L% i
- T c,
- .,A M X 2..QQ..:f *..si 4.+ -.3
~
g
....... a g COOUNQ WATER g_... _,4 : gT..
- c. g ;;; ,,, ';;, 3
=
, = =...,
- -. N _..
3=iE5=:2!!s25_.... J
- 3..-;y:=:= E=.::~:Q
==:::=a_
t:
L Lust OIL LUBE OIL HEAT EXCHANGER 5
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
34 Refer to the drawing of a lube oil heat exchanger (see figure below).
f 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.)
4 A.
increase; decrease B.
increase; increase C.
decrease; decrease D.
decrease; increase I
o i
i
-'g g
- We=:: x1.
_..:==~'W....-
COOU000 WAftR g
,,a,.; ;;; 7 L E i -.7;.-
.._,._..g wen 2.
II.. i.
i
- Q.Q;:.:E2=^~ FEE ~4l
~re
=== r &
LUBEOIL LUBE OIL HEAT EXCHANGER l
USNRC (DENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
35 1
High differential pressure in a demineralizer could be caused by all of the fo] lowing except:
l A.
resin exhaustion.
B.
resin overheating.
C.
crud buildup.
D.
high flow rate.
QUESTION:
36 The ion exchange efficiency of a condensate demineralizer can be determined by:
A.
sampling the inlet and outlet of the demineralizer to determine the difference in radioactivity.
B.
sampling the inlet and outlet of the demineralizer to determine the change in conductivity.
C.
performing a calculation based on the ratio between the inlet pH divided by the outlet pH.
D.
performing a calculation based on the change in differential pressure across the demineralizer.
1 l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
37 A plant is operating at 70% steady state power level when the temperature of reactor coolant letdown passing through a boron-l saturated mixed bed ion exchanger is decreased by 20 F.
As a result, the boron concentration in the effluent of the ion exchanger will because the affinity of the ion exchanger for boron atoms has A.
decrease; increased B.
decrease; decreased C.
increase; increased D.
increase; decreased QUESTION:
'38 Which one of the following describes the normal operation of a local breaker overcurrent trip flag indicator?
A.
Actuates when no lockout is present; satisfies an electrical interlock to remotely close a breaker.
B.
Actuates when a breaker overcurrent trip has occurred; can be manually reset when the overcurrent condition clears.
C.
ActuaLes when a breaker has failed to trip on an overcurrent condition; can be manually reset when the overcurrent condition clears.
i D.
Actuates to cause a breaker trip when the overcurrent trip setpoint is reached; can be remotely reset when the overcurrent i
condition clears.
I USNRC CENERIC FUNDAMENTALS EXAMINA'2 ION APRIL 1997 PWR - FORM A QUESTION:
39 Which one of the following results from c loss of control power to a breaker supplying a motor?
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 of its protective trip device.
D.
Charging motor will not charge the closing spring after the breaker trips open.
l 1
QUESTION:
40 A typical 120 Vac manual circuit breaker has tripred due to I
overload.
To close this circuit breaker tha bleaker handle must be moved from the:
1 A.
OFF position directly to the ON position; trip latch reset is not required.
B.
OFF' position to the midposition to reset the trip latch, and then to the ON position.
j C.
midposition directly to the ON position; trip latch reset is not required.
D.
midposition to the OFF position to reset the trip latch, and then to the ON position.
i USNRC EENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
41 Refer to the drawing of a valve control circuit (see figure below).
Which one of the following describes the purpose of the alarm in the control circuit shown in the accompanying drawing?
A.
Alert the operator when the valve motor circuit has been energized for 10 seconds after pushbutton PB2 is depressed B.
Alert the operator when the valve has not moved off its closed seat within 10 seconds of depressing pushbutton PB2 C.
Alert the operator that the valve is opening by sounding the alarm for 10 seconds after PB2 is depressed D.
Alert the operator if the valve has not reached full open within 10 seconds of depressing pushbutton PB2
+ 125 VDC VALVE PB1 PB2 PosaloN i
(PUSH TO NN o
R o
CLOSE
- 3 j
VALVE) i VALVE)
CONTACT CONTACT 1
I e
a I
e
{
(CLOSED i
1 WHEN I
.Ls1 VALVE
- 2 l
1 FULLY CONTACT i l
l 1
CLOSED) i 1
- ___L_________h
E_
.. ( g3 i
I
_ LS2
__ LS3 TO VALVE (ENERGlZE TO K1 K2
/
MOTOR OPEN VALVE.
(10 SEC (OPEN WHEN (OPEN' CIRCulT DEENERGlZE TIME DELAY VALVE FULLY WHEN TO CLOSE PICKUP)
CLOSED)
VALVE VALVEl
.125 VOC FULLY OPEN)
VALVE CONTROL CIRCUlT 4
l I
\\
UCNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
42 l
I Which one of the following is an unsafe practice if performed when working on or near energized electrical equipment?
l L
A.
Cover exposed energized circuits with insulating material to prevent inadvertent contact.
i B.
Have a person standing by to deenergize the equipment in the event of an emergency.
C.
Use two hands for balance and to prevent dropping tools onto energized equipment.
D.
Stand on insulating rubber material to prevent yourself from being grounded.
QUESTION:
43 A typical main generator is being paralleled to the grid.
Generator voltage equals 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.
Which one of the following will occur after the breaker is closed?
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 remain closed and the generator will become an electrical load on the grid.
D.
The breaker will open due to reverse power.
- -. _ ~ ~.
USNRC CENERIC FUNDAMENTALS EXAMINATION j
APRIL 1997 PWR - FORM A QUESTION:
44 While remotely investigating the condition of a typical normally-f open motor control center (MCC) feeder breaker, an operator observes the following indications:
Green breaker position indicating light is lit.
Red breaker position indicating light is out.
MCC voltmeter indicates zero volts.
MCC ammeter indicates zero amperes.
Based on these indications, the operator can accurately report that the breaker is open and racked to position.
A.
the OUT B.-
the IN C.
the TEST D.
an unknown QUESTION:
45 When comparing a delayed neutron and a prompt neutron born from the same fission event, the prompt neutron is more likely to:
A.
cause fast fission of a U-238 nucleus.
B.
be captured by a U-238 nucleus at a resonant energy between 1 eV and 1000 eV.
C.
be captured by a Xe-135 nucleus.
D.
cause thermal fission of a U-235 nucleus, l
i
USNRC GENERIC FUNDAMENTALS EXANINATION APRIL 1997 PWR - FORM A l
l QUESTION:
46 With K rr = 0.982, how much positive reactivity is required to make e
the reactor critical?
~A.
1.720% oK/K B.
1.767% AK/K t
C.
1.800% AK/K D.
'1.833% AK/K QUESTION:
47 A reactor was operating at 100% power for two months when a reactor trip occurred.
During the 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> since the trip the reactor has been cooled to 340*F and boron concentration has been increased by 200 ppm.
Given the following absolute values of reactivities added during the shutdown and cooldown, assign a (+) or (-) as appropriate and choose the current value of shutdown margin (i.e.,
the amount of reactivity by which the reactor is shut down).
=( ) 2.0% AK/K Boron
=( ) 2.5% AK/K Power defect
=( ) 4.0% AK/K Rods
=( ) 7.0% oK/K Cooldown
=( ) 2.0% oK/K A.
-1.5% oK/K B.
-3.5% AK/K C.
-5.5% AK/K I
D.
-7.5% AK/K l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
48 Positive reactivity is continuously added to a critical reactor.
Which one of.the 'following values of K rt will first result in a prompt critical reactor?
A.
1.0001.
B.
1.001 C.
1.01 D.
1.1 r
i QUESTION:
49 After the first fuel cycle, subcritical multiplication can produce 2
a visible neutron level indication on the source range nuclear instrumentation following a reactor shutdown without installed 3
neutron sources.
This is because a sufficient source of neutrons is being produced by:
A.
spontaneous neutron emission from control rods.
B.
photo-neutron reactions in the moderator.
C.
low level thermal fission in the fuel.
{
D.
alpha-neutron reactions in the fuel, l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
50 Which one of the following conditions will cause the moderator i
temperature coefficient (MTC) to become more negative?
(Consider only the direct effect of the indicated change on MTC.)
A.
The controlling bank of control rods is inserted 5% into the core.
B.
Fuel temperature decreases from 1500 F to 1200*F.
C.
Reactor coolant boron concentration increases by 20 ppm.
D.
Moderator temperature decreases from 500*F to 450*F.
QUESTION:
51 Which one of the following contains the nuclides responsible for most of the resonance captura of fission neutrons in the core at the beginning of the sixth fue' cycle?
(Assume that each refueling replacee one-third of the fuel.)
r A.
U-235 and Pu -239 B.
U-238 and Pu-240 a
U!NRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
52 A reactor is operating at 70% power.
Which one of the following will directly result in a less negative fuel temperature coefficient (FTC)?
(Consider only the direct effect of~the indicated change on FTC.)
A.
Increase in moderator voids B.
Increase in fuel temperature C.
Increase in moderator temperature D.
Increase in Pu-240 inventory in the core 1
l 1
QUESTION:
53 The amount of pure water required to decrease the reactor coolant boron concentration by 20 ppm at the end of core life (100 ppm) is approximately the amount of pure water required to decrease reactor coolant boron concentration by 20 ppm at the beginning of core life (1000 ppm).
A.
one-tenth B.
the same as C.
10 times D.
100 times USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
54 A reactor is critical below the point of adding heat.
If control rods are manually inserted for 5 seconds, reactor power will decrease:
A.
to a shutdown power level low in the source (startup) range.
B.
temporarily, then return to the original value due to the resulting decrease in moderator temperature.
C.
until inherent positive reactivity feedback causes the reactor to become critical at a lower neutron level.
D.
temporarily, then return to the original value due to subcritical multiplication.
QUESTION:
55 l
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 -sec 1
2 Control rod tip thermal neutron flux = 5 x 1028 n/cm -sec 2
If the control rod is slightly withdrawn such that the control rod tip is located in a thermal neutron flux of 1 x 1022 n/cm. 2 l
sec, then the differential control rod worth will increase by a factor of (Assume the core average thermal neutron flux is constant.)
j A.
2 l
B.
4 C.
10 D.
100 e
t. _
UINRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
56 h reactor is operating at 80% power near the end of a fuel cycle with the controlling group of control rods inserted 5% into the Which one of the following will cause group differential core.
rod worth to become less negative?
(Consider only the direct effect of the indicated change.)
h.
Burnable poison rods become increasingly depleted.
j B.
The reactor coolant system (RCS) temperature is allowed to decrease from 575*F to 570*F.
C.
Core Xe-135 concentration decreases toward an equilibrium
- value, i
D.
Reactor power is decreased to 70% using control rods for control of RCS temperature.
l l
QUESTION:
57 A reactor is operating at 75% power with all control rods fully withdrawn.
Assuming reactor power does not change, which one of the following compares the effects of dropping (full insertion) a single center control rod to the effects of partially inserting i
l (50%) the same control rod?
~
l A.
A dropped rod causes a smaller change in axial power distribution.
l B.
A dropped rod causes a smaller change in radial power I
distribution.
C.
A dropped rod causes a smaller change in shutdown margin.
D.
A dropped rod causes a greater change in shutdown margin.
9
... ~.
d g
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A 4
QUESTION:
58 A fission product poison can be differentiated from all other fission products in that a fission product poison:
A.
will be radioactive for thousands of years.
B.
is produced in a relatively large percentage of thermal fissions.
t C.
has a relatively high probability of absorbing a fission neutron.
~ D.
is formed as a gas and is contained within the fuel pellets and fuel rods.
a
)
QUESTION:
59 Which one of the following indicates that core Xe-135 is in equilibrium?
1 A.
Xe-135 production and removal rates are momentarily equal five hours after a power increase.
B.
A reactor has been operated at 80% power for five days.
C.
Xe-135 is being produced equally by fission and I-135 decay.
D.
A reactor is currently operating at 100% power.
1 1
1 USNRC GENERIC FUNDAMENTAL 3 EXAMINATION APRIL 1997 PWR'- FORM A QUESTION:
60 A reactor had been operating at 50% power for two weeks when power was increased to 100% over a 3-hour period.
In order to maintain reactor power stable during the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, which one of the following incremental control rod manipulations will be required?
A.
Withdraw rods slowly during the entire period 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 i
a j
QUESTION:
61 A reactor has been operating at 75% power for two months.
A manual reactor trip is required for a test.
The trip will be followed immediately by a reactor startup with criticality scheduled to occur 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the trip.
The greatest assurance that xenon reactivity will permit criticality during the startup will be attained if the reactor is operated at power for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the trip and if criticality is rescheduled for hours after the trip.
A.
100%; 8 B.
100%; 16
)
C.
50%; 8 D.
50%; 16 1
.- _ - =...
1 USNRC @ENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
62 A reactor has been shut down for 5 days to perform maintenance.
A reactor startup is performed and power ir ramped to 75% over a 16-hour period.
When power reaches 75%, the magnitude of core xenon-135 negative reactivity will be:
A.
decreasing toward a valley.
B.
increasing toward a peak.
C.
decreasing toward equilibrium.
D.
increasing toward equilibrium.
1 I
i QUESTION:
63 A reactor has been operating at 100% power for two weeks.
Power is then decreased over a 1-hour period to 10%.
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 1
i D.
Add negative reactivity, then positive reactivity
)
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
64 Why are burnable poisons installed in a reactor core?
A.
To shield reactor fuel from thermal neutron flux until later in core life B.
To compensate for control rod depletion that occurs over core
' life C.
To flatten the axial thermal neutron flux distribution early in core life D.
To ensure that the control rods will be above the rod insertion limit when the reactor is critical QUESTION:
65 During a reactor startup, the first reactivity addition caused the count rate to increase from 20 to 40 cps.
The second reactivity addition caused the count rate to increase from 40 to 80 cps.
Assume K rr was 0.92 prior to the first reactivity e
addition.
l Which one of the following statements describes the magnitude of the reactivity additions?
i A.
The first reactivity addition was approximately twice as large as the second.
B.
The second reactivity addition was approximately twice as large as the first.
C.
The first and second reactivity additions were approximately l
the same.
D.
There is not enough data given to determine the relationship between reactivity values.
4 d
5._
_ -. ~.
USNRC GENERIC FUNDAMENTALS EXAMINATICN APRIL 1997 PWR -- FORM A QUESTION:
66 Near the end of core life, critical rod position has been calculated for a reactor startup 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a trip from 100%
power equilibrium conditions.
The actual critical rod position will be lower than the predicted critical rod position if:
A.
the startup is delayed until 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the trip.
B.
one control rod remains fully inserted during the approach to criticality.
C.
actual boron concentration is 10 ppm higher than the assumed boron concentration.
D.
steam dump is used to lower main steam pressure by 20 psi just prior to reactor startup.
l QUESTION:
67 l
A reactor is critical several decades below the point of adding heat-(POAH) when a small amount of oositive reactivity is added to the core.
If the exact same amount of necative reactivity is then added to the core prior to reaching the POAH, reactor power will stabilize:
A.
higher than the initial power level but below the POAH.
B.
lower than the initial power level.
C.
at the initial power level.
I l
D.
at the POAH.
1 4 l
USNRC EENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
68 A reactor is stable at the point of adding heat (POAH) with the reactor coolant at 550*F during a plant startup.
Control rods are withdrawn a few' inches to increase steam generator steaming rate.
When the reactor stabilizes, reactor power will be and reactor coolant temperature will be
_ 550*F.
A.
above the POAH; equal to B.
above the POAH; greater than C.
at the POAH; equal to D.
at the POAH; greater than QUESTION:
69 i
Which one of the following power changes requires the smallest amount of positive reactivity addition?
A.
3% power to 5% power B.
5% power to 15% power C.
15% power to 30% power D.
30% power to 60% power i
i USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
70 l
A reactor is operating with the following initial conditions:
Power level
= 100%
Coolant boron
= 620 ppm l-Coolant temperature = 587*F After a load decrease reactor conditions are as follows:
Power level
= 80%
Coolant boron
= 650 ppm Coolant temperature = 577 F All parameters were at normal steady-state values before and after_the power change.
Given the following, how much reactivity was added by control rod movement during the load decrease?
(Assume fission product poison reactivity does not change.)
Differential boron worth
= -1. 0 x 10-2% AK/K/ ppm Total power coefficient
-1. 5 x 10-2% AK/K/%
=
Moderator temperature coefficient
-2. 0 x 10-2% AK/K/*F
=
A.
-0.0% AK/K B.
-0.2% AK/K i
C.
-0.6% AK/K l
D.
-0.8% AK/K l
l i
)
4 i
l l
1 USNRC EENERIC FUNDABENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
71 Following a reactor trip, reactor power indicates 0.1% when the typical stable post-trip reactor period is observed.
Which one of the following is the approximate time required for reactor power to decrease to 0.05%?
A.
24 seconds B.
55 seconds C.
173 seconds D.
240 seconds l
QUESTION:
72 After one month of operation at 100% reactor power, the fraction of thermal power being produced from the decay of fission products in the operating reactor is:
A.
less than 1%.
B.
greater than 1% but less than 5%.
C.
greater than 5% but less than 10%.
l p
D.
greater than 10%.
I l
l l
i USNRC GENERIC FUNDAMENTAI.S EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
73 Which~one of the following is the approximate condenser-vacuum
.when condenser pressure is 16 inches Hg absolute?
A.
4 inches Hg vacuum B.
8 inches Hg vacuum' C.
12 inches Hg vacuum D.
14 inches Hg vacuum F
i QUESTION:
-74 i
. Consider _a pressurizer containing a saturated water / steam mixture at 636*F with a quality of 50%.
If an outsurge removes 10% of the:11guid volume from the pressurizer, the temperature of the mixture will and the quality of the mixture will (Assume the mixture remains saturated.)
)
A.
decrease; decrease B.
decrease; increase
'C.
remain the same; decrease D.
remain the same; increase l
l l
1 l l l
USNRC GENERIC FUNDADENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
75 A plant is shut down with the pressurizer in a saturated condition with liquid and vapor temperatures at 650 F.
After a reactor coolant system cooldown, pressurizer conditions are as follows:
Pressurizer liquid temperature = 588'F Pressurizer vapor temperature
= 607 F Pressurizer pressure
= 1410 psia Given these conditions, the pressurizer liquid is and the pressurizer vapor is A.
subcooled; saturated B.
subcooled; superheated C.
saturated; saturated D.
saturated; superheated QUESTION:
76 Which one of the following explains why condensate subcooling is necessary in the steam turbine / condenser phase of a plant cycle?
A.
.To provide a better condenser vacuum B.
To maximize overall secondary efficiency C.
To provide net positive suction head for the condensate pumps D.
To minimize turbine blade and condenser tube erosion by entrained moisture l
l l l
USNRC @ENERIC FUNDAMENTALS EXAMINATION 1
APRIL 1997 PWR'- FORM A i
QUESTION:
77 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 j
steadily rising.
The pr'essurizer vapor space contains 96%
. quality saturated steam and PORV downstream pressure is 20 psia.
Assuming PORV leakage is an ideal throttling process, which one of the following will be the. approximate PORV-tailpipe temperature if a PORV is leaking byi A.
228'F B.
258*F C.
284*F D.
322*F QUESTION:
78 If superheating of the inlet steam to a low pressure turbine is reduced, low pressure turbine work output will and low pressure turbine exhaust steam moisture content will (Assume steam flow rate does not change.)
A.
remain the same; increase B.
remain the same; decrease C.
decrease; increase D.
decrease; decrease l
l l
i I
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
79 A 60 gpm leak has developed in a cooling water system that is operating at 150 psig.
Which one.of the following will be the leak. rate when system pressure has decreased to 75 psig?
A.
15.0 gpm B.
30.0 gpm C.
42.4 gpm D.
53.1 gpm 8
QUESTION:
80 The maior concern with starting a feedwater pump with downstream fluid in a saturated condition is:
A.
cavitation.
B.
C, thermal shock.
D.
positive reactivity addition.
I I
l- !
l
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
81 Refer to the drawing of a cooling water system in which only pump A is operating and the pump discharge valve is currently 50% open (see figure below).
Which one of the following will cause pump A to operate closer to the conditions that will cause cavitation?
A.
Starting pump B B.
Positioning the discharge valve to 40% open C.
Raising the water level in the surge tank by 2. feet D.
Increasing heat exchanger service water flow rate by 10%
P
?AW HEAT EXCHANGEM E :
LOADS W
R LOADS PUMP A COOLING WATER SYSTEM l
I i.
_s UCNRC (EEMERIC FUNDAMENTALS 27.ANINATION l
APRIL 1997 PWR - FC'AN A QUESTION:
82 i
8 A reactor coolant system is supplying 1.0 x 10 lbm/hr of coolant flow at a temperature of 100*F.
Assuming volumetric flow rate does not change, which one of the following is the approximate mass flow rate that will be supplied by the system if coolant temperature increases to 500*F?
8 A.
1.21 x 10 lbm/hr 8
B.
1.13 x-10 lbm/hr 7
C.
8.7 x 10 lbm/hr 7
D.
7.9 x 10 lbm/hr l
f QUESTION:
83 Two centrifugal pumps and two positive displacement pumps are able to be cross connected to provide flow in a system.
Each pump will produce 100 gpm at 1000 psig system pressure and each pump has a design naximum pressure of 1500 psig.
If system pressure is 1200 psig, which one of the following will produce the greatest system flow rate?
A.
Two centrifugal pumps in series B.
Two centrifugal pumps in parallel C.
Two positive displacement pumps in series D.
Two positive displacement pumps in parallel i
i
f UONRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUEFTION:
84 Which one of the following pairs of fluids undergoing heat transfer through a heat exchanger will yield the greatest heat e:: changer overall heat transfer coefficient?
A.
Oil to water B.
Air to water C.
Steam to water D.
Water to water QUESTION:
85 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 coolant pump heat input term was omitted from the heat balance calculation.
C.
The steam and feedwater flow rates used in the heat balance I
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 pressure.
~.
USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
86 I
1 Which one of the following is a characteristic of subcooled nucleate boiling but not saturated nucleate boiling?
A.
Tel a equals Ts t i
B.
T el o i s g r e a t e r t h a n T s,e C.
Tsutw co 2,ne equals Ts,e t
D.
Taulk coolane is less than Ts,e f
i t
l
[
i e
t f
QUESTION:
87 Which one of the following will be the initial cause of fuel 3
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 P
1 l'
I USNRC EENERIC FUNDANENTALS EXANINATION APRIL 1997 PWR - FORN A QUESTION:
88 Refer to the drawing of a pool boiling curve (see figure below).
Which one of the following describes the conditions in a fuel channel that is experiencing region III heat transfer?
A.
Complete steam blanketing of the fuel rod surface B.
Alternate wetting and drying of the fuel rod surface C.
Saturated nucleate boiling D.
Subcooled nucleate boiling i
ll 111 IV i
i I
LOG HEAT FLUX 1
LOG AT 1
POOL BOILING CURVE l
l l
l l
~
USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
89 Which one of the following describes the relative contributions of the convective and radiative heat transfer mechanisms during stable film boiling heat transfer in the core?
A.
Only the radiative heat transfer mechanism is significant and AT increases exponentially with heat flux.
B.
Only the radiative heat transfer mechanism is significant and AT increases in direct proportion.to heat flux.
C.
Both heat transfer mechanisms are significant and AT increases exponentially with heat flux.
D.
Both heat transfer mechanisms are significant and AT increases in direct proportion to heat flux.
L QUESTION:
90 t
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 maximum 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 i
-. _. ~
USNRC GENERIC FUNDAMENTALS EXAMINATION i
APRIL 1997 PWR - FORM A i
QUESTION:
91
(
Single-phase coolant flow resistance (head loss) in a reactor l
core is directly proportional to coolant and inversely i
proportional to
{
l A.
temperature; coolant channel cross-sectional area l
B.
temperature; fuel assembly length C.
velocity; coolant channel cross-sectional area D.
velocity; fuel assembly length l
1 1
l i
l l
{
l QUESTION:
92 Fully-developed natural circulation flow rate will be greatest
)
when:
A.
all reactor coolant pumps stop at the same time the reactor trips.
B.
all reactor coolant pumps stop sequentially within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after a reactor trip.
C.
all reactor coolant pumps run for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after a reactor trip, and then stop.
D.
only one reactor coolant pump runs for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after a reactor trip, and then stops.
4
USNRC' GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORN A QUESTION:
93 A reactor coolant system cooldown is in progress on natural circulation via the steam generator (S/G) atmospheric steam relief valves (operated in manual control).
If high point voiding interrupts natural circulation, which one of the following trends will occur?
(Assume feed flow rate, relief valve position, and decay heat level are constant.)
A.
S/G level increases and S/G pressure increases.
B.
S/G level increases and S/G pressure decreases.
C.
S/G 1evel decreases and S/G pressure increases.
D.
S/G. level decreases and S/G pressure decreases.
QUESTION:
94 Which-one of the following describes the basis for the 2200*F maximum fuel clad temperature limit?
l A.
The material strength of zircaloy decreases rapidly at l
temperatures above 2200*F.
l l
B.
At the normal operating pressure of the reactor vessel a clad I
temperature above 2200*F indicates that the critical heat l
flux has been exceeded.
C.
The rate of the zircaloy-water reaction becomes significant at temperatures above 2200*F.
D.
2200*F is approximately 500 F below the fuel clad melting l
temperature.
1
.. _ _ _. - - _ _ - _ _ = _
- ~
USNRC GENERIC FUNDAMENTALS EXAMINATION APP.IL 1997 PWR - FORM A QUESTION:
95 Which one of the following describes the fuel-to-coolant thermal conductivity for a fuel assembly at the beginning of core life (BOL) as compared to the end of core life (EOL)?
A.
Larger at BOL due to a higher fuel pellet density B.
Larger at BOL due to lower contamination of fuel rod fill gas with fission product gases C.
Smaller at BOL due to a larger gap between the fuel pellets and clad D.
Smaller at BOL due to a smaller corrosion film on the surface of the fuel rods l
l QUESTION:
96 Brittle fracture of the reactor vessel (RV) is least likely to occur during a of the RV when RV temperature is the reference temperature for nil-ductility transition (RTee).
A.
cooldown; above B.
heatup; above l
C.
cooldown; below D.
heatup; below l
4
- ~.. - -. - - - -..... -..
1 USNRC GENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
97 i
Which one of the following describes the stress placed on the reactor vessel during a cooldown of the reactor coolant system?
A.
Compressive at the inner wall, tensile at the outer wall j
B.
Tensile at the inner wall, compressive at the outer wall C.
Compressive across the entire wall D.
Tensile across the entire wall 1
I l
i i
QUESTION:
98 After several years of operation, the maximum allowable stress to the reactor vessel is more limited by the inner wall than the outer wall because:
A.
there is a temperature gradient across the reactor pressure vessel wall.
B.
the inner wall has a smaller surface area than the outer wall.
C.
the inner wall experiences more neutron-induced embrittlement than the outer wall.
l D.
.the inner wall experiences more tensile stress than the outer wall.
I I
l USNRC CENERIC FUNDAMENTALS EXAMINATION APRIL 1997 PWR - FORM A QUESTION:
99 Two identical reactors have been in operation for the last 10 l
years.
Reactor A has experienced 40 heatup/cooldown cycles with an average power capacity of 50%.
Reactor B has experienced 30 heatup/cooldown cycles with an average power capacity of 60%.
Which reactor will have the lowest reactor vessel nil-ductility i
i l
transition temperature?
A.
Reactor A due to the lower average power capacity j
B.
Reactor A due to the greater number of heatup/cooldown cycles i
C.
Reactor B due to the higher average power capacity i
D.
Reactor B due to the fewer number of heatup/cooldown cycles i
QUESTION:
100 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?
f A.
A rapid depressurization followed by a rapid heatup B.
A rapid depressurization followed by a rapid cooldown C.
A rapid cooldown followed by a rapid pressurization i
D.
A rapid heatup followed by a rapid pressurization i
1 I
i e
4 i !