ML19325E861
| ML19325E861 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/01/1989 |
| From: | Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Holmes K GEORGIA POWER CO. |
| References | |
| NUDOCS 8911090213 | |
| Download: ML19325E861 (78) | |
Text
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p NUCLEAR nt2VLATORY c0MMisslON p
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ATLANT A, OEORGI A 30323 November 1, 1989 Docket Nos. 50-424 and 50-425 Georgia Power Company ATTN: Mr. K. Holmes Training Manager Nuclear Operations Training Center J
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Vogtle Electric Generating Plant Route 2. Box 299A.
Waynesboro, GA 30830 GENTLEMEN:
On October 4 )1989. -the NRC administered the Generic Fun Section (GFES of the written operator licensing examination to employees of your facility.
Enclosed with this letter are copies of both forms of the examination including answer keys, the grading results for your facility, and copies of the individual answer sheets for each of the examinees from your facility who took the examination.
Please forward the results and answer sheet to the examinees. A "P" in the column labeled Final Grade indicates a passing grade for this examination; passing grade for the GFES is 80 percent.
, ['
In accordance with 10 CFR 2.790 of the Connission's Regulations, a copy of this letter and Enclosures 1 and 2 will be placed in the NRC's Public Document Y
Room (PDR). The results for individual examinees are exempt from disclosure.
therefore. Enclosures 3 and 4 will not be placed in the PDR.
Should you have any questions concerning this examination, please contact L
Mr. Paul Doyle at (301) 492-1047.
1 L
Sincerely, d
/s.Thomask.c.Peebles.' Chief c__
l 7" Operations Branch Division of Reactor Safety
Enclosures:
i 1
1.
Examination Fonn "A" with Answers 2.
Examination Form "B" with Answers 3.
Examination Results Sunnary for Facility 4.
Copies of Candidates Individual Answer Sheets Hf9'S M
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1 ANSWER KEY I
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26.
A.
51.
D.
-76.
B.
2.
D.
27.'
D.
52.
C.
77.
D.
3.
A.-
28.
D.
53.
B.
78.
D.
4.
D.
M 54.
D.
79.
B.
7 5.
B.
30.
A.
55.
A.
80.
C.
6.
B.
31.
B.
M 81.
C.
7.
D.
32.
C.
57.
B.
82.
C.
8.
C.
33.
A.
58.
D.
83.
A.
1 9.
C.
34.
C.
59.
B.
84.
D.
10.
B.
35.
A.
60.
B.
85.
B.
11.
B.
36.
D.
61.
B.
86.
D.
12.
D.
37.
C.
62.
D.
87.
C.
13.
C.
38.
C.
63.
D.
88.
A.
44,==4W' 39.
B.
64.
A.
89.
B.
15.
C.
4 0..
D.
65.
D.
90.
D.
16.
D.
41.
B.
66.
D.
91.
D.
I 17.
D.
42.
B.
67.
B.
92.
A.
18.
C.
43.
A.
68.
C.
93.
A.
19.
B.
44.
B.
69.
B.
94.
B.
20.
B.
45.
A.
70.
D.
95.
A.
21.
C.
46.
A.
71.
C.
96.
B.
22.
C.
47.
C.
72.
C.
97.
B.
23.
B.
48.
A.
73.
D.
98.
A.
24.
B.
49.
D.
74.
A.
99.
A.
25.
D.
50.
A.
75.
D.
100. D.
Pressurized Water Reactor,eneric Fundamentals Examination 1
r administered October 4.1989.
Questions 14, 39 and 56 I
were deleted.
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77.
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35.
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86.
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62.
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87.
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13.
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B.
63.
A.
88.
B.
14.
D.
39.
B.
64.
D.
89.
B.
15.
C.
40.
D.
65.
C.
90.
D.
16.
A.
41.
C.
66.
C.
91.
D.
17.
B.
67.
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92.
A.
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D.
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44.
D.
69.
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94.
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20.
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45.
D.
70.
B.
95.
B.
21.
A.
46.
C.
71.
A.
96.
C.
22.
B.
47.
B.
72.
B.
97.
B.
23.
A.
48.
B.
73.
A.
98.
D.
24.
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74.
A.
99.
C.
1 25.
B.
50.
C.
75.
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100.
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Pressurized Water Reactor Generid Fundamentals Examination administered October 4, 1989.
Questions 42, 57 and 84 were deleted.
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4 UNITED STATES NUCLEAR REGULATORY COMMISSION PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION Please Print:
.Name:
Facility:
ID Number:
4 INSTRUCTIONS TO CANDIDATE Use the answer sheet provided.
Each question has equal point value.
The passing grades require at least 80% on this part of the written licensing examination. All examination papers will be picked up 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the examination starts.
SECTION Questions 4 of Total Score COMPONENTS 1
43 REACTOR THEORY 44 - 72 THERMODYNAMICS 73 100 TOTALS 100 All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature L
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RULES AND GUIDELINES FOR THE CENERIC 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 the facility you are associated with.
'(3)
Fill in the ID Number you were given at registration, t
(4) Three handouts are provided for your use during the examination, an Equations and Conversions sheet, instructions for filling out the answer sheet, and Steam Table booklets.
(5) Use only the answer sheet provided.
Credit will only be given for answers marked on this sheet.
Follow the instructions for filling out the answer sheet.
(6) Scrap paper will be provided for calculations.
(7) Any questions about an item on the examination should be directed to the examiner only.
(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, please 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) Please turn in your examination materials answer sheet on top followed by the exam 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 examiner.
If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeited.
- 0 CENDLIC FUNDAMETAIA EIANIMATION SECTION
- o SQUATIONS AND CONVERSIONS HANDOUT SHEET EDUAT10HS i
Cycle Efficiency = Net Work (out)
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PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA1Ji EXAMINATION F.-
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QUE'ST10N:
1.
i The primary purpose of a pressure relief salve is to:
a 4
A.
maintain system flow, f
B.
maintain system pressure.
C, maintain system integrity.
D.
maintain system temperature.
W f
QUESTION:
2.
s
.When a discharge-valve is opened to atmosphere, the pressure on the upstream
-side of.the' valve will:
A.
remain the same, and the pressure on the downstream side will increase.
B.
. increase,.and the pressure on the downstream side will remain the same.
C.
' remain the.same, and the pressure on the downstream side will decrease.
D.
decrease, and the pressure on the downstream side will remain the same, i
. QUESTION:
3.
The function.of a valve backseat is to:
isolate system pressure from the packing and stuffing box to minimize A.
{
packing leakage.
l B.
, isolate system pressure from the packing and stuffing box for the purpose of valve repacking.
C.
provide a backup means of flow isolation in the event of primary seat leakage.
provide a backup means of flow isolation in the event of a pipe break,
.D.
i 1
FORM A Page 1 of 35 9
j
PRESSURIZED WATER REACTOR CENERIC WNDAMDffA12 EXAMINATION FORM A l
f QUESTION:
4.
After manually positioning a motor operated valve, how is the valve actuator j
~
re engaged?
)
A.
Actuation of the torque switch i
B.
Manually pulling up on the manual declutch lever
[
C.
Actuation of either the full.open or full. closed limit switch j
D.
Actuation of the valve actuator motor in either the open or close direction l
QUESTION:
5.
To verify the position of a closed manual valve, the operator should operate the valve:
A.
to the fully open position, then reclose it using normal force.
(
B.
in the closed direction using normal force.
J C.
in the open direction until flow sounds are heard, then close the valve using manual force, j
D.
in the closed direction until it stops, then close it an additional j
one half turn using normal force, j
i QUESTION:
6.
Density compensation is used in flow instruments to change to l
t A.
mass flow rate, volumetric flow rate B.
volumetric flow rate, mass flow rate C.
fluid pressure, volumetric flow rate D.
differential pressu,re, mass flow rate i
1 1
FORM A Page 2 of 35
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.h PRESSURIEF.D WAf t3L RfACTOR CDtERIC FUNDAMENTA1A EKANIMATION 4
FORN A
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- , o QUESTION:
7.
j e
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If the liquid flowing through a liquid flow rate sensor contains entrained i
voids (gas or steam), indicated flow rate will be:
j A.
erroneously high.
B.
erroneously low,
+
i C.
unaffected.
t D.
fluctuating,
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QUESTION:
8.
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If the equalizing line on a differential pressure (D/P) flow detector is opened, the flow detector indication will:
A.
increase slightly.
l l,
B.
decrease slightly.
j i
C.
go to zero.
D.
not change.
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QUESTION:
9.
Flow detectors (such as an orifice, flow nozzle, and venturi tube) measure flow rate using the principle that flow rate is:
l A.
DIRECTLY proportional to the differential pressure.
j i
B.
INVERSELY proportional to the differential pressure, e
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C.
DIRECTLY proportional to the square root of the differential pressure.
D.
IEEE%1ELI proportional to the square root of the differential pressure.
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FORM A Page 3 of 35 l
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PRES $URIZED WATER REACTOR CENERIC WNDAMDfTALS EKAMINATION FORM A QUESTION: 10.
The pressure differensial between a reference leg and a variable leg is:
A.
DIRECTLY proportional to the height of the variable leg.
[
B.
INVERSELY proportional to the hei ht of the variable leg, j
t C.
p1RECTLY proportional to the density of the reference leg.
D.
INVERSELY proportional to the temperature of the reference leg.
QUESTION: 11.
If the reference leg of a differential pressure level indicator experiences high ambient temperature, fr.dicated level will:
A.
read less than actual level.
B.
read greater than actual level.
C.
equal the actual level.
D.
slowly decrease to zero.
QUESTION: 12.
r The level indication for a reference leg differential pressure level instrument will fail LQW as a result of:
A.
a break on the reference leg.
l l
B.
a rupture of the diaphragm in the differential pressure cell, j
C.
the reference leg flashing to steam.
l D.
a break on the variable leg.
I i
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i PORM A page 4 of 35 r
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f PRES $URIEED WATER REACTOR CENERIC MMDAMENTALS BAMINATION i
FORN A QUESTION:
13.
A resistance temperature detector (RTD) operates on the principle that the
[
change in electrical resistance of:
A.
two dissimilar metals is DIRECTLY proportional to the temperature change l
measured at their junction.
l B.
two dissimilar metals is INVERSFL*! proportional to the temperature change measured at their junction.
5 C.
a metal is D1J9,f W proportional to its change in tenperature.
D.
a metal is INVERSELY proportional to its change in temperature.
j QUESTION:
14.
Two differential pressure level transmitters are installed in a large tank.
I If transmitter I is calibrated at 200 'F and transmitter II is calibrated at 100 'F. then at 150.'F:
A.
transmitter I will read greater than transmitter II.
B.
transmitter II will read greater than transmitter I.
C.
transmitter I and II will read the same, D.
it is impossible to predict how either transmitter will respond, i
i QUESTION:
15.
t Scintillation detectora operate on the principle of:
A.
photodisintegration.
B.
photokinesis.
C.
photomultiplication.
D.
photoionization, t
i i
FORM A Page 5 of 35
L';
I PRESSUIt1EED WATI3t REACTOR CDirJt1C IWDAMENTA1.S EKAMINATION f
PORM A l
l QUESTION:
16.
A BF3 proportional counter detects both neutrons and gammas. Which of the following best describes the method used to eliminate the Samma contribution fcom the detector output?
j A.
Two counters are used, one sensitive to neutron and gamma and the other sensitive to gamma only. The outputs are electrically opposed to cancel i
the gamma. induced currents and yield a neutron only signal for indication
- use, t
B.
The BT3 proportional detector records neutron flux of sufficient intensity that the gamma signal is insignificant compared to the neutron signal and yields a neutron.only signal for indication use.
[
i C.
Gamma. induced detector pulses are of insufficient width to generate a i
significant log. level amplifier output. Neutron pulses are the only ones i
with sufficient width to yield a neutron.only signal for indication use.
D.
Neutron. induced current pulses are significantly larger than those from r
gamma. The detector signal is applied to a circuit which filters out the smaller gamma pulses yielding a neutron.only signal for indication use.
QUESTION:
17.
The difference between the setpoint and the measured parameter in an automatic l
flow controller is called-A.
gain.
B.
bias.
C.
feedback.
D.
- error, t
QUESTION:
18.
A controller's output is typically insufficient to accurately drive a valve actuator. To overcome this problom, a control loop normally employs:
A.
a lead / lag unit.
B.
a regulator.
C.
a positioner.
D.
an amplifier unit, t
PORM A Page 6 of 35
l,.
FILES $UtttED WATDL REACTOR CDIERIC ftINDAMDtTALE EKAM1MATION PORM A l-QUESTION:
19.
Why must an operator pay particular attention to auto / manual valve controllers left in the manual mode?
A.
The manual valve control is usually not stable compared to the automatic mode.
B.
The valve position vili no longer respond to changes in system parameters.
C.
The controlled parameters will no longer be controlled by the valve position.
D.
The valve can only be operated locally during this time.
QUESTION:
20.
What precautions must be observed when transferring a valve controller from the automatic mode to manual mode of control?
A.
Ensure that the proper offset is established between the automatic mode and manual mode.
B.
Ensure that the valve controller output signals are matched between aatomatic mode and manual mode.
C.
Ensure that the valve controller stabilizes in the automatic mode before completely transferring to the manual mode of control.
D.
Ensure that the automatic valve controller signal is increasing before transferring to manual mode of control.
QUESTION:
21.
An indication of centrifugal pump cavitation is:
A.
pump motor amps pegged high.
B.
pump discharge pressure indicating zero.
C.
pump motor amps oscillating.
D.
pump discharge pressure indicating shutoff head.
FORM A Page 7 of 35 i
I
p' l
PRESSURIEED ilATER REACTOR CDfERIC FUNDAMENTALS EXAMINATION FORM A j
l QUESTION:
22.
t The term " shutoff head' for a centrifugal pnsp indicates that it is pumping at:
j A.
natinum capacity and minimum discharge head.
l l
B.
maximum capacity and maximum discharge head.
l C.
minimum capacity and maximum discharge head.
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D.
minimum capacity and minimum discharge head.
l f
QUESTION:
2J.
Operating a motor driven centrifugal pump for extended periods of time with no l
flow through the punip will cause:
A.
pump failure from overspeed.
B.
pump failure from overheating, t
i C.
motor failure from overspeed.
D.
motor failure from overheating.
QUESTION:
24 SKUTTING the discharge valve on an operating centrifugal pump will cause the MOTOR AMPS to and the pump PISCHARGE PRESSURE to e
A.
increase, increase B.
decrease, increase i
C.
increase, decrease D.
decrease, decrease i
i FORM A Fage 8 of 35 L
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PRES $l5llEED WATFJL REACTOR CDIERIC PVitDANOfTALS EKAMINATIOW L
PORM A s
QUESTION: 2$.
i, If the speed of a positive displacement pump is increased, the available net l
positive suction head (NPSH) will and the probability of l
cavitation will __
l A.
increase, increase t
B.
decrease, decrease l
C.
increase, decrease i
D.
decrease, increase l
QUP.$ TION: 26.
t l
Reactor coolant pump motor amps will if the rotor is LOGEED and the motor speed will
,_,if the rotor EME&RI.
l l
A.
increase, increase B.
increase, decrease i
C.
decrease, increase l
t D.
decrease, decrease h
i QUESTION:
27.
i if the generator bearings on a motor generator overheat then:
A.
the generator voltage will increase.
i B.
the generator windings will overheat.
?'
C.
the motor current will decrease.
i D.
the motor windings will overheat.
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FORM A Page 9 of 35 1
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PRES $UR11ED WATER REACTOR CDftRIC WNDAMENTA1.8 RIAMINATION l
PORN A
?
QUESTION: 28.
If the speed of a variable speed centrifugal pump is increased to cause pump flow rate to double, rump motor current will.
f A.
remain constant.
B.
increase two. fold (double).
j r'
C.
increase four. fold.
i D.
increase eight. fold.
I f
.I QUESTION: 29.
The starting current in an A.C. notor is significantly higher than the full load running current because:
l t
A.
starting torque is lower than running torque.
B.
starting torque is higher than running torque.
l i
C.
rotor current during start is higher than running current.
D.
rotor current during start is lower than running current, j
l QUESTION:
30.
t The number of starts for an electric motor in a given period of time should be limited because:
l i
A.
overh6 sting of the windings can occur.
B.
excessive torque is generated during motor start.
C.
running current is much higher than starting current.
D.
motors are normally started under full load conditions.
i i
P E
FORM A Page 10 of 35 i
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PRESSURIEED WATER REACTOR CDfERIC FUlfDAMDrfALS EKAMINATION PORM A QU4STION:
31.
Severe stress in a mechanical component induced by a sudoen, unequally distributed temperature reduction is a description of:
A.
heat stress.
B.
thermal shock.
C.
thermal strain.
L.
heat strain.
QUESTION:
32.
Tube fouling in a heat exchanger causes heat transfer to decrease by:
A.
reducing fluid velocity on the shell side of the exchanger.
B.
increasing flow rate through the tube side of the exchanger.
C.
reducing the overall (total) heat transfer coefficient.
D. increasing the overall (total) heat transfer coefficient.
l QUESTION:
33.
Borated water is flowing through the tubes of a heat exchanger being cooled by fresh water.
The shell side pressure is less than tube side pressure. What will occur as a result of a tube failure?
A.
Depletion of borated water inventory.
B.
Depletion of cooling water inventory.
e C.
Dilution of the borated water system.
D.
Shell pressure will decrease.
P FORM A Page 11 of 35 i
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i 1
FRESSUR1EED WATER REACTOR CDIERIC nlNDAMENTALS EKAMINATION l
QULSTION:
34.
j i
l What is the reason for bypassing a desineralizer due to high temperature?
i A.
Resins expand and restrict flow through the denineralizer.
l r
B.
The dentneralizer decontaminatt.on factor is dramatically increased.
C.
Organic compounds used as resins vill decompose, i
D.
The creation of preferential flovpath through the demineralizer will t
occur.
QUESTION:
35.
In the event of a system crud burst, what adverse effect does the crud burst have on deafneralizer operation?
A.
Increases pressure drop across demineralizer B.
Increases flow rate through desineralizer C.
Increases demineralizer outlet conductivity l
D.
Increases demineralizer inlet pH QUESTION:
36.
Boron concentration in the reactor (primary) coolant system has been i
decreasing steadily at approximately 10 ppa per hour while using the deborating desineralizer. After several hours, the rate decreases to 2 ppm per hour. What is a possible cause for the change in deboration rate?
A.
Temperature of the coolant passing through the demineralizar has decreased.
B.
pH of the coolant has increased significantly.
C.
Flow through the deborating resins has increased sharply.
D.
Deborating resins have become boron saturated, i
l l
l l
FORM A Page 12 of 33
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t l PRESSURIZED WATFR REACTOR CDIERIC IVNDMtENTALS EXAMINATION j
g1 PORM A l
i QUESTION:
37.
I t
To do.energine a component and its associated control and indication circuits, r
the component circuit breaker should be:
t sn A.
racked in and tagged in open position.
l l
l B.
racked in and tagged in closed position.
l C.
racked out and tagged in racked out position.
D.
in the test position and tagged in test.
l QUESTION:
38.
I To ensure reliable local breaker indication is being provided the sust be reset after breaker operation.
A.
OPEN/Cl4 SED nechanical flag B.
OPEN/CIASED indicating lights C.
Overcurrent trip flag
[
D.
Spring CHARCE/DISCR@CE flag QUESTION:
39.
l i
A circuit breaker thermal overload device:
i A.
compares actual current to a fixed overcurrent setpoint that is equated l
to temperature and actuates a trip relay.
i B.
when subjected to high current, overhaats and actuates a
(
circuit interrupting device.
j C.
senses operating equipment temperature and trips protective circuits at f
preset limits.
D.
is an induction coil that produces a secondary current proportional to
[
the primary current.
f i
FORM A Page 13 of 35 1
A PRESSURIZED WATI3t REACTOR CENERIC WNDAMENTALS EXAMINATION FORM A
[
QUESTION:
40.
I Loss of circuit breaker control power will cause:
(
i A,
breaker line voltage to be zero regardless of actual breaker position, j
l b.
the remote breaker position to indicate closed regsrdless of actual
[
breaker position.
l C.
inability to operate the breaker locally and remotely, f
t D.
failure of the close spring to charge following local tripping of the
- breaker, j
r QUESTION:
41.
If a de. energized bus is not unloaded prior to closing the output breaker of a three phase generator onto the bus, then:
A.
an overvoltage condition will occur on the bus, j
B.
an overcurrent condition will occur on the generator.
j t
C.
an overvoltage condition will occur between generator phases.
l D.
generator undervoltage relay actuation will occur.
t QUESTION:
42.
Which of the following statements is correct concerning the use of disconnect
[
switches?
i A.
Disconnects should be limited to normal load current interruption.
{
B.
Disconnects may be used to isolate transformers in an unloaded network.
I 1
C.
Disconnects are similar to oil circuit breakers, but are manually operated.
D.
Disconnects must be closed with caution when under load because of j
possible arcing.
P P
l FORM A Page 14 of 35
--s FILES $UR1EED tdATElt ILEACTOR CDtIRIC PVNDAMENTALS EXANIMATICII i
t FORN A L.
t QUESTION:
43.
l Closing a generator output breaker with the generator frequency much less than grid frequency vill cause the generator to trig
- on:
l l
A.
reverse power.
r I
B.
overvoltage, i
O.
I
.D.
QUESTION: 44 The operator has just pulled control rods and changed the effective multipli.
cation factor (K,fg) from 0.998 to 1.002. The reactor is:
i A.
prompt critical j
B.
supercritical i
C.
exactly critical e
D.
suberitical i
i i
I t
e i
t f
t t
i l'
1 PDitN A Page 1$ of 35
PRES $URIEED WATER REACTOR Cf3lERIC FUNDM4DffAl.S EXAMINATION
]
PORM A c,-
QUESTION:
45.
J The ratio of the number of neutrons in one generation to the number of neutrons in the previous ' generation is the:
A.
effective multiplication factor B.
fast fission factor i
C.
neutron non leakage factor D.
neutron reproduction factor QUESTION:
46.
Reactivity is defined as the:
A.
fractional change in neutron population per generation.
B.
nuniber of neutrons by which neutron population changes per generation.
C.
rate of change of reactor power in neutrons per second.
D, change in the number of neutrons per second that causes a fission event.
QUESTION:
47.
A given amount of positive reactivity is added to a critical reactor in the source (startup) range. The amount added is less than the average effective delayed neutron fraction. Which of the following vill have a significant effect on the ma5nitude of the stable startup rate achieved for this addition?
A.
Prompt neutron lifetime B.
Fuel temperature coefficient c.
Average effective decay constant D.
Moderator temperature coefficient FORM A Page 16 of 35
. - ~...
'I E,
PRESSURIEED WAtlat REACTOR CENDtIC IWDAMENTA1A EKAMINATION
- e PORM A QUESTION
48.
i Over core life the production of plutonium isotopes with delayed neutron fractions,_
than uranium delayed neutron fractions will csure reactor power transients to be _
near the end of core life, i
s A.
less, faster 8.
less, slower
+
I C.
greater, faster D.
. greater, slower i
t t
QUESTION:
49.
- t An installed neutron source:
A.
saintains the production of neutrons high enough to allow the reactor to achieve criticality.
B.
provides a means to allow reactivity changes to occur in a suberitical I
reactor.
C.
generates a sufficient neutron population to start the fission process and initiate suberitical sultiplication.
r D.
provides a neutron level that is detectable on the source range nuclear instrumentation.
i QUESTION:
50.
Why does increasing reactor coolant boron concentration cause the moderator temperature coefficient to become less negative?
s A.
Reactor coolant temperature increases result in a larger increase in the l
thermal utilization factor.
B.
Reactor coolant temperature increases result in an increase in the resonance escape probability.
C.
Reactor coolant temperature increases result in an increase in the total
[
non leakage probability.
i D.
The change in resonance escape probability dominates the change in the thermal utilization factor.
FORN A page 17 of 35 t
I i
PRES $URIZED WATI3t REACTOR CDfDLIC FUNDARDf7ALS RAMINATION p
FORN A
/
QUESTION:
51.
Why does the fuel tenpersture (Doppler) coefficient becomes less negative at higher fuel temperatures?
A.
As reactor power increases, the rate of increase in the fuel temperature l
diminishes.
B.
Neutrons penetrate deeper into the fuel, resulting in an increase in the I
fast fission factor.
C.
The amount of self shielding increases, resulting in less n.utron absorption by the inner fuel.
l i
D.
The amount of Doppler broadening per degree change in fuel temperature I
diminishes.
l QUESTION:
52.
A reactivity coefficient measures change while a reactivity defect (deficit) measures a change in reactivity due to a change in the measured parameter.
i A.
An integrated, total l
B.
A race of, differential C.
A differential, total D.
A total, differential QUESTION:
53.
During power operation, while changing power level, core reactivity is affected most quickly by:
A.
boron concentration adjustments.
l l
B.
power defect (deficit).
I C.
D.
fuel depletion.
l l
IVRM A page 18 of 35
. ~- __ _
PRES $URIZED WATI:R REACTOR CDIERIC WIfDAnl:NTALS EKAMINATION FORT 1 A l
L t
t QUESTION:
$4 i
As moderator terperature increases, the msgnitude of differential rod (CLA) l J
worth increases because:
L A.
decreased moderator density causes more neutron leakage out of the core.
B.
moderator temperature coefficient decreases, causing decreased f
I corpetition.
t C.
fuel temperature increases, decreasing neutron absorption in fuel.
j D.
decreased moderator density increases neutron migration length.
QUESTION:
55.
Control rod (CLA) bank overlap:
provides a more uniform differential rod (CEA) vorth and axial flux A.
distribution.
B.
provides a more uniform differential rod (CEA) worth and allow dampening of Xenon induced flux oscillations.
C.
ensures that all rods (CEAs) remain within the allowable tolerance between their individual position indicators and their group counters and to ensure rod (CEA) insertion limits are not exceeded.
D, ensures that all rods (CEAs) remain within their allowable tolerance between individual position indicators and their group counters and to provide a more uniform axial flux distribution.
QUESTION:
$6.
The basic for the maximum power density (kw/ft) power limit is to:
A.
prevent fuel clad melt.
B.
prevent fuel pellet melt.
C.
limit bulk coolant temperature.
D.
prevent nucleate boiling.
FORM A Page 19 of 35
~ - -
l t
FRES$URIZED WATEF. REACTOR CENERIC fvNDAMDf7ALS EKAMINATION i
FORM A
[
QUESTION:
57.
l The control rod insertion limits are power. level dependent because the magnitude of:
j A.
control rod worth decreases as power increases.
i B.
power defect increases as power increases, j
f C.
Doppler (fuel temperature) coefficient decreases an power increases, i
D.
moderator temperature coefficient increases as power increases, f
i
(
QUESTION:
58.
j Fission producte that have substantial neutron capture cross sections are:
l A.
excited fission products.
B.
fission product daughter.
C.
radioactive fission products.
D.
fission product poisons.
l r
QUESTION:
59.
Fo11owin6 a reactor trip from sustained high power operation, Xenon 135 concentration in the reactor will:
l A.
decrease because Xenon is produced directly from fission.
B.
increase due to the decay of Iodine already in the core.
C.
remain the same because the decay of Iodine and Xenon balance each other out.
1 D.
decrease immediately, then slowly increase due to the differences in the half lives of Iodine and Xenon.
i-i FORM A page 20 of 35
x_-
PRESSURIEED WATER REACTOR CDfERIC FUNDAMDffALS EXAMINATION FORK A L
QUESTION: 60.
Following a reactor trip from sustained high power operation, the major Xenon 135 removal process is:
A.
ion exchange.
B.
beta decay.
l C.
neutron capture.
(
l D.
alpha decay.
j i
f QUESTION:
61.
l A reactor has been operating at 50. percent power for 7 days when power is raisped to 100 percent over a four hour period. The new equilibrium Xenon value will:
t A.
be twice the 50 percent value, j
i B.
be less than twice the 50 percent value.
C.
be more than twice the 50 percent value.
l 1
D.
remain the same since it is independent of power.
l l
f QUESTION:
62.
f t
Slow changes in axial power distribution in a reactor that has operated at a steady state power for a long time can be caused by:
A.
Xenon peaking.
B.
Xenon override.
C.
Xenon burnup.
D.
Xenon oscillation.
i
(
e i
i FORM A Page 21 of 35
-v-
,w-vv----
PILES $UR1EED WATER REACTOR CDtERIC WNDAMDf7ALS ERAMINATION s
FORN A QUESTION:
63.
A reactor that has been operating at rated power for about two weeks reduces power to 50 percent. Xe.135 will reach a new equilibrium condition in hours.
A.
8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> B.
20 to 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> C.
30 to 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> D.
40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> QUESTION:
64 The reactor is near the end of its operating cycle.
In order to stay critical, power and temperature have been allowed to "coastdown." Why is boron no longer used to compensate for fuel depletion?
A.
Boron concentration approaches zero and requires excessive amounts of water to dilute.
B.
The differential boron worth has decreased below its useable point, C.
The boron in the coolant has been depleted due to neutron absorption.
D.
'Coastdown" is preferred due to fuel conditioning limitations.
QUESTION:
65.
While withdrawing control rods during an approach to criticality, the count rate doubles. What will occur if the same amount of reactivity that caused the first doubling is added againt A.
Count rate will increase slightly.
l B.
Count rate will double.
C.
The reactor will remain suberitical.
1 D.
The reactor will be critical or slightly supercritical.
l FORN A Page 22 of 35 l
l
y-i, -. '
I MLESSURIEED WATER REACTOR CENERIC mtD.9tDf7AtJ UAMINATION FORM A QUESTION:
66.
i f'
in a reactor with a source, a non. changing neutron flux over a few minutes is
[
indicative of criticality or:
r A.
the point of adding heat.
a.
supercriticality, i
C.
suberiticality, i
D.
equilibrium suberitical count rate.
QUESTION:
67.
At E01., critical rod (CEA) position has been calculated for a reactor startup i
four hours af ter a trip from 100 percent power equilibrium conditions. The i
i actual critical rod (CEA) position will be la'ER than the predicted critical rod (CEA) position if:
[
A.
the startup is delayed until eight hours after the trip.
B.
the steam dump pressure setpoint is lowered by 100 psi prior to reattor
{
startup.
C.
actual boron concentracion is 10 ppm more than the assumed boron j
concentration.
D.
one control rod (CEA) remains fully inserted during the approach to criticality.
QUESTION: 68.
criticIff-0.985,howmuchreactivitymustbeaddedtomakethereactor With k e
A.
1,480 pcm (1.484 delta k/k) i B.
1,500 pcm (1.50% delta k/k) 0, 1,520 pcm (1.52% delta k/k)
D.
1,540 pcm (1.54% delta.k/k) t i
I
(
FORM A Page 23 of 35
I
~
1 l
[
PRESSURIEED WATER REACTOR CENERIC PVNDANDITA1A EIANIMATION l
PORN A f
QUESTION:
69.
[
If. during's reactor startup, the startup rate is con, tant and positive j
without any further reactivity addition, then the reactor is:
A.
critical.
B.
supercritical, j
C.
suberitical, r
D.
prompt critical.
QUESTION:
70.
Civen a critical reactor operating below the point of adding heat. What l
reactivity effects are associated with reaching the point of adding heat?
4 A.
There are no reactivity effects since the reactor is critical, j
B.
The increase in fuel temperature will begin to create a positive reactivity effect.
C.
The decrease in fuel temperature will begin to create a negative reactivity effect.
i D.
The increase in fuel temperature will begin to create a negative reactivity effect.
l 1
i i
QUESTION:
71.
Shortly after a reactor trip reactor power indicates 0.5 percent where a l
stable negative SUR is attained. Reactor power will be reduced to 0.05 percent in approximately seconds.
t 7
A.
360 l
B.
270 C.
180 L
D.
90 e
FORM A Page 24 of 35 I
~ -.
p r
a' l
FRESSURIEED WATDt RFACTOR DENERIC FUNDAMENTALS EKAMINATION FORM A
'h QUESTION:
72.
1 The major reason boron is used in a reactor is to permit:
A.
a reduction in the shutdown margin.
l B.
an increase in the amount of control rods (CEAs) installed.
I C.
an increase in core life.
D.
a reduction in the effect of resonance capture, i
l i
1 1
i o
i i
t t
I l
i
(
's l
I, i
I' 1,
1 l
l l,
I l~
t i
PVRM A Page 25 of 35 1
,I PItr.ssultittD UATEit REAC1tIIt Catu1C MINDARDtTALS EKANINATION FCILM A.
QUESTION:
73.
An atmospheric pressure of 15 psia equals:
l i
A, 30 psig.
B.
15 psig, i
C.
5 psig.
D.
O psig.
l i
QUESTION:
74 I
Condensate depression is defined as:
A.
cooling the condensate below its saturation temperature.
B.
saintaining the condensate at a constant temperature throughout the
- system, i
l C.
ensuring that the condensate is below the level of the hotwell pumps.
D.
cooling the condensate to the point of saturation.
QUESTION:
75.
t l
What is the reactor coolant system subcooling for Tave - 400'F and pressurizer pressure - 1,000 psia?
[
i A.
75'F l
B.
100'F C.
125'T f
D.
145'F i
I l
e FORM A Page 26 of 35 l
G l
i FRESSURIEED WATDt REACToet CmERIC 7JNDAMDffA13 EKAMINAT1008 f
o f
FORM A i
1.
QUESTION: 76.
(
The plant is saintained at 2,000 psia with a pressurizer temperature of 636*F.
A pressurizer safety reitet valve is leaking to a collection tank which is i
being held at 10 psig. Vhat is the temperature of the fluid downstream of the relief valve 7 1
A.
280'F B.
240'F t
I C.
'190'r D.
170'r i
i QUESTION:
77.
overall plant efficiency will DECREASE if:
A.
the steam quality la increased by removing moisture fro:s the steam prior
[
to entering the turbine.
l B.
the temperature of the feedwater entering the steam generator is increased.
C.
the amount of condensate depression (subcooling) in the main condenser is decreased.
i
.D, the temperature of the steam at the turbine inlet is decreased.
I QUESTION:
78.
'"he possibility of a water hammer is MINIMIZED by:
l A.
char.ging valve positions as rapidly as possible.
l l
B.
starting centrifugal pumps with the discharge valve fully open.
l C.
starting positive displacement pumps with the discharge valve closed.
i D.
venting systems prior to starting centrifugal pumps l
l 1
l l-FORM A Page 27 of 35 l
l
i PRESSURIEED MTER REACTOR CENERIC FUNDANDrrA14 MANIMATION A
o QUESTION:
79.
Cavitation in an operating pump may be caused by:
i A.
Iowering the suction temperature.
8.
throttling the pump suction valve.
t C,
throttling the pump discharge valve.
D.
increasing the pump discharge pressure, f
I QUESTIO":
80, i
The piping system pressure change caused by suddenly stopping fluid flow is referred to as:
A.
cavitation.
t B.
shutoff head, C,
D.
flow head.
t QUESTION:
81.
If a flow measuring instrument is HQI density compensated, then indicated mass flow rate will be:
A the same as actual mass flow rate with a change in temperature of the fluid.
i B.
grer.ter than actual mass flow rate with a decrease in temperature of the fluid.
C.
less than actual mass flow rate with a decrease in temperature of the
{
- fluid, r
D.
less than actual mass flow rate with an increase in temperature of the fluid.
r s
FORN A Page 28 of 35
t h
l PRESSURIZED WATER REAC1VR CDiERIC IVNDAMENTALS EEAMINATION FORM A l
QUESTION:
82.
Operating two pumps in parallel instead of operating a single pump will result l
in:
A.
a large increase in system head and the same flow rate.
f B.
the same system head and a small increase in flow rate.
{
C.
a small increase in system head and a lar5e increase in flos rate.
D.
a decrease in system head and a large increase in flow rate, j
i t
QUESTION:
83.
Excessive amounts of entrained gases passing through a single. phase (liquid) heat exchanger is UNDESIRABLE because:
A.
flow blockage can ocer.r in the heat exchanger.
B.
t.he laminar layer will increase in the heat exchanger.
C, the heat transfer coefficient will increase in the heat exchanger.
the temperature difference across the tubes will decrease through the D.
heat exchanger.
QUESTION:
84 In a two loop pressurized water reactor, feedwater flow to each steam generator is 3.3 x 10 lba/hr at an enthalpy of 419 BTU /lba. The steam exiting each steam generator is at 800 psia with 100% steam quality.
Ignoring blowdown and pump heat, what is the core thermal power?
A.
3,411 Wt B.
2,915 We C.
2,212 We D.
1,509 We IDRM A Page 29 of 35
(57 a
l 1
PRESSURIZED WATER REACTOR GENERIC WNDAMENTALS EKAMINATION L[
FORM A
(
I QUESTION:
85.
Why does nucleate boiling improve heat transfer in the core?
A.
The formation of steam bubbles at nucleation sites on the fuel clad allows more heat to be transferred by conduction.
l B.
Heat is removed from the fuel rod as both sensible heat and latent heat of vaporization, and the motion of the steam bubbles cause rapid mixing of the coolant.
C.
Heat is removed from the fuel rod as both sensible heat and latent heat of condensation, and the heat is transferred directly to the coolant by radiative heat transfer.
D.
The formation of steam bubbles at nucleation sites on the fuel clad reduces' coolant flow in that area and allows more heat to be transferred by convection.
QUESTION:
86.
Subcooled nucleate boiling is occurring along a heated surface. The heat flux is then increased slightly.
What will be the effect on the delta T between the surface and the fluid?
A.
Large increase in delta T because of steam blanketing B.
Large increase in delta T causing radiative heat transfer to become significant C.
Small increase in delta T because of steam blanketing D.
Small increase in delta T as vapor bubbles form and collapse L
T l
l l
QUESTION:
87.
lanat parameter change would move the plant farther away from the critical heat i
l flux?
[
A.
Decrease pressurizer pressure 1
l B.
Decrease reactor coolant flow C.
Decrease reactor power D.
Increase reactor coolant tr >erature FORM A Page 30 of 35 1
,,n..,
,n
i i
F
['o PRESSURIZED WATER REACTOR CENERIC MINDAMENTAIE EKAMINATION I
FORM A I
L QUESTION:
88.
Film boiling is:
'A.
heat transfer through a vapor blanket that covers the fuel cladding.
J B.
heat transfer being accomplished with no phase change.
C.
the most efficient method of boiling heat transfer.
D, heat transfer through an oxide film on the cladding.
QUESTION:
89.
The departure from nucleate boiling ratio (DNBR) is defined as:
A.
the actual heat flux divided by the critical heat flux at any point along a fuel rod.
B.
the critical heat flux divided by the actual heat flux at any point along 1
a fuel rod..
l' C.
the core thermal power divided by the total reactor coolant mass flow rate.
D.
the number of coolant channels that have reached DNB divided by the number of coolant channels that are subcooled.
1 1^
QUESTION:
90.
The reactor coolant'subcoeling margin will be PIRECTLY. REDUCED by: (Evaluate each change separately.)
A.
increased pressurizer pressure.
1 L
B.
increased pressurizer level.
1 C.
increased reactor coolant flow.
i D.
increased reactor coolant temperature.
l FORM A Page 31 of 35
PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION FORM A QUESTION: '91.
Maximizing the. elevation difference between the core thermal center and the steam generator thermal centers and miniraizing flow restrictions in the reactor coolant system (RCS) piping are plant designs to:
A.
minimize the reactor coolant system volume.
B.
maximize the reactor coolant system flow rate during forced circulation.
I L
C..
ensure a maximum RCS loop transit time.
D.
ensure RCS natural circulation flow can be established.
QUESTION:
92, i
With the RCS subcoolad and all RCPs stopped, the natural circulation flow rate will NOT be affected by an increase in the:
A.
reactor coolant pressure increase.
B.
time after reactor trip.
C.
steam generator level increase.
D.
steam generator pressure decrease i
QUESTION:
93.
If departure from nucleate boiling (DNB) is reached in the core, the surface temperature of the fuel clad will:
l-A.
increase rapidly.
B.
decrease rapidly.
l I
C.
increase gradually.
D.
decrease gradually.
l lI l
l l
l l
l l
l FORM A Page 32 of 35 l
NN
]-
1 PRESSUR1 ZED WATER REACTOR CENERIC MINDAMENTA13 EKAMINATION PORN A i
- i..
L QUESTION:
94
[
if the reactor is operated within core thermal limits, then:
I 1
. A.
plant thermal efficiency is optimized.
b.
fuel cladding integrity is ensured.
f C.
Pressurized thermal shock will be prevented.
i D.
Reactor vessel thermal stresses will be minimized.
+
i QUESTION:
95, t
Fast neutron irradiation of the reactor vessel results in stresses within the vessel metal, thereby the Nil Ductility Transition Temperature.
A.
increased, increasing E.
increased, decreasing C.
decreased, increasing D.
decreased, decreasing l
QUESTION:
96, e
The likelihood of brittle fracture failure of the reactor vessel is REDUCED by:
A.
increasing vessel age.
l B.
reducing vessel pressure.
C.
reducing vessel temperature.
i D.
reducing gamma flux exposure.
l l
FORM A Page 33 of 35
y PRESSURIZED WATER REACTOR CENERIC WNDAME!TTALS EKAMINATION FORM A J
QUESTION:
97.
Pressure stress on the reactor vessel wall is:
f A.
compressive across the entire wall.
a: -
B.
tensile across the entire wall.
C.
tensile at the inner vall, compressive at the outer wsil.
D.
compressive at the inner all, tensile at the outer wall.
(
QUESTION:
98, t
The nil ductility temperature is that temperature:
A.-
below which the probability of brittle fracture significantly increases.
B.
where failure stress becomes greater than the yield stress of the metal.
C.
below which the probability of plastic deformation significantly increases.
D.
below which the yield stress of the metal is higher than the critical fracture stress.
QUESTION:
99.
Pressurized thermal shock could most likely be a concern during:
A.
an uncontrolled cooldown followed by a rapid repressurization.
B.
an uncontrolled depressurization followed by a rapid repressurization.
C.
an uncontrolled cooldown followed by a rapid depressurization.
D.
an overpressurization from a low temperature, low pressure condition.
FORM A Page 34 of 35
1.' c
.j PRESSURIZED WATER REACTOR CDIERIC WNDAMENTALS EKAMINATION FORN A QUESTION:. 100.
During a severe overcoolin5 transient, a major concern to the operator is:
L A.
' accelerated zirconium hydriding.
f B.
loss of reactor vessel water level, C.
loss of reactor coolant pump net positive suction head.
I
~
D.
brittle fracture of the reactor vessel.
.i p
~
t L
t i
i
\\
a.
i FORM A Page 35 of 35
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3 bc l
UNITED STATES' NUCLEAR REGULATORY COMMISSION PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION d
Please Print:
Namn:
Facility:
ID Number:
INSTRUCTIONS TO CANDIDATE Use the answer sheet provided.
Each question has equal point value. The.
passing grades require at least 806 on this part of the written licensing examination. All examination papers will be picked up 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the examination starts.
l SECTION Questions t of Total Score i
THERMODYNAMICS 1 - 28 COMPONENTS 29 '71 REACTOR THEORY 72 100
[
s l
l TOTALS 100 l'
L l
All work done on this examination is my own.
I have neither given nor received aid.
l'.
l L
Candidate's Signature 0
l' FORM B l
i RULES AND CUIDELINES FOR THE CENERIC 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, u
t (2) Fill in the name of the facility you are associated with.
(3) Fill in the ID Number ysu were given at registration.
(4) Three handouts are provided for your use during the examination, an Equations and Conversions sheet, instructions for filling out the answer
~
sheet, and Steam Table booklets.
($) Use only the answer sheet provided, credit will only be given for answers marked on this sheet.
Follow the instructions for filling out the answer sheet.
?
(6) Scrap paper will be provided for calculations.
(7) Any questions about an item on the examination should be directed to the examiner only.
(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) After you have completed the examination, please 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) Please turn in your examination materials answer sheet on top followed by the exam 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 examiner.
If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeited.
r
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1 I
CENERIC FUNDAMETAIJ FEAMINATION SECTION l
.,1 BQUATIONS AND CONVERSIONS MANDOUT SHEET j,
I EXhTIMS
- k
=
a* e AT Cycle Efficiency Net Work fout) 1 p
Energy (in) 4 5 Ah SCR S/(1 K,gg)
=
?
k' - UA AT CRg (1 K,gg)g CR2 (1
- Keff)2 SUR - 26.06/r M
1/(1 K,gg)
CR /CR g
0 26.06 (A,gg p)
(1. K,gg)0 (i.p)
(1. K,gg)g SUR(t)
P P, 10 SDM (1. K,gg)/K,gg.
=
=
P,a(*/")
.Pwr = 'V i
l P
g L
(1*/p)'+ [(i p)/A,gg ]
1*/(p - A) r p
r t
I (K,gg 1)/K,gg 1*
1 x 10 5 seconds i
p 1
0 p-AK,gg/K,gg A,gg = 0.1 seconds i
L 1
h I
CONVERSIGHS 10 1 Curie 3.7 x 10 dps 1 kg 2.21 lba 3
6 1 hp 2.54 x 10 BTU /hr 1 Mw 3.41 x 10 BTU /hr i
^?
i 1 BTU 778 ft lbf
'F f/5 *C + 32
=
l~
- C 5/9 (F 32) 1 l
' y,l ',*.
r, PRESSURIZED WATER REACTOR' CDIERIC Ft!NDAMENTALS EXAMINATION roRM B l
QUESTION: '1.
t An atmospheric pressure of 15 psia equals:
A.-
30 psig.
.i.
B.
15 psig.
'C.
'5 psig.
D.
O psi 8 0
-QUESTION:
2.
Condensate' depression is' defined as:
A.
cooling the condensate below its saturation temperature.-
B.
maintaining the condensate at a constant temperature throughout the system.
C4 ensuring that the condensate is below the level of the hotwell pumps.
D.
cooling the. condensate to the point of saturation,
- r. p i
~ UESTION:
3.
Q 1
What is the reactor coolant system subcooling for Tave - 400'F and pressurizer pressure - 1,000 psia?
L-A.
75'F l
1.' '
B, 100*F l'
t C.
125'F D.
145*F i
p l'
l' L
l..
g lgJ f
l i
l 1
FORM B Page 1 of 34 L
... _. ~,.. _ _. ~.... _. _.. _ _ _. _. _ _ _ _ _ _ _ _
i~
v
- i'
[
PRESSURIZED WATER REACTOR' CDfERIC FUNDAMENTALS EKAMIKhTION
, i.. g NB QUESTION:.
4.
The plant is. maintained at 2,000 psia with a pressurizer temperature of 636'r.
n.
- A pressuriger safety relief valve is leaking to a collection tank which is being4 held at 10 psig. What is the temperature of the fluid downstream of the r
relief valve?.
j
- A..
280'F-
. i B.
240'F C.
190*F Ih 170'F
~
QUESTION:
5.
Overall plant efficiency will DECREASE if:
4 A.
the steam quality is increased by removing moisture from the steam prior
{
to entering the turbine.
the temperature of the feedwater entering the steam generator is B.
increased.
a the amount of condensate depression (subcooling) in the main condenser is C.
l '.
decreased.'
. t D.
the. temperature of the steam at the turbine inlet is decreased.
1 t
QUESTION:
6.
l The possibility of a water hammer is MINIMIZED by:
l j'
A.
changing valve positions as rapidly as possible, l'
1 B.
- . starting centrifugal pumps with the discharge valve fully open.
l j.
C.
starting positive displacement pumps with the discharge valve closed.
l-D.
venting systems prior to starting centrifugal pumps.
- 1..
1 j '.s l
l-PORM B Page 2 of 34 L
p'
. ~....,. _., -... -. _..,. -...
E 4/
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. PRESSUR1EED WATR REACTOR CRRIC WNDAMENTALS MANINATION
.it; t
' QUESTION:
7.
j Cavitation in an operating pump may be caused by:
j
.A.
Iowering the suction temperature.
B.
throttling the pump suction valve.
.i C.
throttling the pump discharge valve.
2' D.
increasing the pump discharge pressure, w
QUESTION:
8.
i The piping system pressure change caused by suddenly stopping fluid flow is
(
referred to as:
A.
cavitation.
B.
shutoff head.
C.-
x D.
flow head.
1 i
QUESTION:
9.
-If a flow measuring instrument is HQI density compensated, then indicated mass flow rate will be:
LA.
the same as actual mass flow rate with a change in temperature of the fluid-
-l B.
greater than actual mass flow rate with a decrease in temperature of the fluid.
C.
less than actual mass flow rate with a decrease in temperature of the fluid.
P D.
less than actual mass flow rate with an increase in temperature of the p
fluid.
1 1'
1.[
i
([
1 l
l.
FORM B Page 3 of 34 n
,a PRESSURIZED WATER REACTOR CENERIC PVNDAMENTAIE EKAKINATION i
FORM B QUESTION:
10.
h Operating two pumps in parallel instcad of operating a single pump will result in:
A.
a'large increase in system head and the same flow rate.
B.
the same system head and a small increace in flow rate.
i C.
a small increase in system head and a'large increase in flow rate.
D.
a decrease in system head and a large increase in flow rate.
QUESTION:
11.
Excessive amounts of entrained gases passing through a single-phase (liquid) heat exchanger is 1DiDESIRABLE because:
A.
flow blockage can occur in the beat exchanger.
B.
the laminar layer will increase in the heat exchanger.
C.
the heat transfer coefficient will increase in the heat exchanger.
D.
the temperature difference across the tubes will decrease through the heat exchanger.
[
QUESTION:
12.
In a two loop pressurized water reactor, feedwater flow to each steam generator is 3.3 x 10 lba/hr at an enthalpy of 419 BTU /lba. The steam exiting each steam generator is at 800 psia with 1004 steam quality.
Ignoring blowdown and pump heat, what is the core thermal power?
A.
3,411 MWt B.
2,915 MWt C.
2,212 MWt D.
1,509 MWt j
1 FORK B Page 4 of 34
]
+
l s
PRESSURIZED WATER REACMR CENRIC WNDAMENTALS EKANINATION FORM &
J QUESTION:
13.
i Why does nucleate boiling improve heat transfer in the core?
A.
The formation of steam bubbles.st nucleation sites on the fuel clad allows more heat to be transferred by conduction.
B.
Heat is removed from the fuel rod as both sensible heat and latent heat of vaporization, and the motion of the steam bubbles cause rapid mixing of the coolant.
C.
Heat is removed from the fuel rod-as both sensible heat and latent heat of condensation, and the heat is transferred directly to the coolant by radiative heat transfer.
D.
The formation of steam bubbles at nucleation sites on the fuel clad reduces coolant flow in that area and allows more heat to be transferred by convection.
QUESTION:
14.
~
h Subcooled nucleate boiling is occurring along a heated surface.
The heat flux is then increased slightly. What will be the effect on the delta-T between the surface and the fluid?
A.
'Large increase in delta T because of steam blanketing B.
Large increase in delta T causing radiative heat transfer to become significant l
C.
Small increase in delta-T because of steam blanketing L
D.
Small increase in delta-T as vapor bubbles form and collapse QUESTION:
15.
f What parameter change would move the plant farther away from the critical heat I
flux?
l A.
Decrease pressurizer pressure B.
Decrease reactor coolant flow C.
Decrease reactor power L
D.
Increase reactor coolant temperature FORM B Page 5 of 34
i' PRESSURIZED WATER ret.CTOR CENERIC WNDAMENTALS EKAMINATION FORM B QUESTION:
16.
Film boiling.is:
A.
heat transfer through a vapor blanket that covers the fuel cladding.
{
B.
heat transfer being accomplished with no phase change.
C.
the most efficient method of boiling heat transfer.
D.
heat transfer through an oxide film on the cladding, l
QUESTION:
17.
The departure from nucleate boiling ratio (DNBR) is defined as:
A.
the actual heat flux divided by the critical heat flux at any point along a fuel rod.
B.
the critical heat flux divided by the actual heat flux at any point along a fuel rod.
C.
the core thermal power divided by the total reactor coolant mass flow rate.
D.
the number of coolant channels that have reached DNB divided by the number of coolant channels that are subcooled.
QUESTION:
18.
The reactor coolant subcooling margin will be DIRECTLY REDUCED by: (Evaluate I
each change separately.)
A.
increased pressurizer pressure.
B.
increased pressurizer level.
C.
increased reactor coolant flow.
l l
D.
increased reactor coolant temperature.
l l
l l
1 FORM B Page 6 of 34
.. ~..
i 1
FRESSURIZED VATER REAC'!OR GENERIC FUNDAMENTALS EXAMINATION urn B 1
QUESTION:
19.
Maximizing the elevation difference between the core thermal center and'the steam generator thermal centers and minimizing flow restrictions in the i
reactor coolant system (RCS) piping are plant designs to:
A.,
minimize the reactor coolant system volume.
B.
maximize the reactor coolant system flow rato during forced circulation.
C, ensure a maximum RCS loop transit time.
D.
ensure RCS natural circulation flow can be established.
QUESTION:
20.
With the RCS subcooled and all RCPs stopped, the natural circulation flow rate will llQI be affected by an increase in the:
A.
reactor coolant pressure increase.
B.
time after reactor trip.
C.
steam generator level increase.
D.
steam generator pressure decrease.
t QUESTION:
21.
I If departure from nucleate boiling (DNB) is reached in the core, the surface temperature of the fuel clad will:
A.
increase rapidly.
B.
decrease rapidly.
C.
increase gradually.
D.
decrease gradually.
FORM B Page 7 of 34
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b
F-
, PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA!E EKANINATION mg I
LQUESTION:
22.
]
If the reactor is operated within core thermal limits, then:
i r
i A.
plant thermal efficiency is optimized, B.-
fuel'eladding integrity is ensured.
]
e C.
pressurized thermal shock will be prevented.
?
I D.
-reactor vessel thermal stresses will be minimized.
l l
LQUESTION:
23.
Fast neutron irradiation of the reactor vessel results in stresses
~ c'
'within the vessel metal, thereby the Nil Ductility Transition Temperature.
A.
increased, increasing B.
increased, decreasing C.
decreased, increasing D.
decreased, decreasing
- 3 i,
. QUESTION:
24.
The likelihood of brittle fracture failure of the reactor vessel is REDUCED o
by:
A, increasing vessel age.
B.
reducing vessel pressure.
C.
reducing vessel temperature.
D.
reducing gamma flux exposure, 1
l.
l L
l L
I FORM B Page 8 of 34 3
9, PRESSURIZED WATER REACTOR CENERIC WNDAMENTALS EXAMINATION PORM B i
QUESTION:
25.
Pressure stress on the reactor vessel wall is:
A.
compressive across the entire wall.
B.
tensile across the entire wall.
)
)
C.
tensile at the inner wall, compressive at the outer wall.
D.
compressive at the inner all, tensile at the outer wall.
QUESTION:
26.
]
The nil ductility temperature is that temperature:
A.
below which the probability of brittle fracture significantly increases.
B.
where failure stress becomes greater than the yield stress of the metal.
4 c.
below which the probability of plastic deformation significantly increases.
1 D.
below which the yield stress of the metal is higher than the critical fracture stress.
QUESTION:
27.
l Pressurized thermal shock could most likely be a concern during:
I A.
an uncontrolled cooldown followed by a rapid repressurization, B.
an uncontrolled depressurization followed by a rapid repressurization.
C.
an uncontrolled cooldown followed by a rapid depressurization.
D.
an overpressurization from a low temperature, low pressure condition.
QUESTION:
- 2. 8.
During a severe overcooling transient, a major concern to the operator is:
A.
accelerated zirconium hydriding.
B.
loss of reactor vessel water level.
C.
loss of reactor coolant pump net positive suction head.
D.
brittle fracture of the reactor vessel.
1 FORM B Page 9 of 34 1
-(i W
a
)
1 1
' PRESSURIZED WATER REACTOR CENERIC WNDAMENTALS EKAMINATION o
FORM B
]
QUESTION:
29.-
The primary purpose of a pressure relief valve is to:
1 i
A.
maintain system flow, i
B.
maintain system pressure.
j C.
maintain system integrity, D.
maintain system temperature.
i i'
QUESTION:
30.
When a discharge valve is opened to atmosphere, the pressure on the upstream side of.the valve will:
{
A.
remain the same, and the pressure on the downstream side will increase.
B.
increase, and the pressure on the downstream side will remain the same.
C.
remain the.same, and the' pressure on the downstream side will decrease.
D.
decrease..and the pressure on the downstream side will remain the same.
[
QUESTION:
31, i
The function of a valve backseat is to:
i A.
' isolate system pressure from the packing and stuffing box to minimize packing leakage.
B.
isolate system pressure from the packing and stuffing box for the purpose L
of valve repacking, i,
C.
provide a backup means of flow isolation in the event of primary seat l
1eakage.
,1 D.
provide a backup means of flow isolation in the event of a pipe break.
L L.
1.
l l
l 1:
H 1 ~-
FORM B Page 10 of 34 1
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I
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PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EKAMINATION l
FORM B i
QUESTION:
32.
After manually positioning a motor-operated valve, how is the valve actaator re engaged?
j A..
Actuation of the torque switch B.
Manually pulling up on the manual declutch lever
{
C.
Actuation of either the full open or full closed limit switch j
D.
Actuation of the valve actuator actor in either the open or close direction QUESTION:
33.
To verify the position of a closed manual valve, the operator should operate the valve:
A.
to the sully open position, then reclose it using normal force.
B.
in the closed direction using normal force.
C.
in the open direction until flow sounds are heard, then close the valve using ranual force.
D.
in the closed direction until it stops, then close it an additional one half turn using normal force.
QUESTION:
34.
Density compensation is used in flou instruments to change to A.
mass flow rate, volumetric flow rate B.
volumetric flow rate, mass flow rate l
l C.
fluid pressure, volumetric flow rate D.
differential pressure, mass flow rate l
l 1.
l FORM B Page 11 of 34 l
.. [ :(
PRESSURIEED WATER REACTOR GENERIC PUNDAMENTALS EKAMINATION -
FORM B QUESTION:
35.
.If the liquid flowing through a liquid flow rate sensor contains entrained voids (gas or steam).. indicated flow rate will be:
A.
erroneously high.
B.
erroneously low.
C, unaffected.
D.
fluctuating.
?'
. QUESTION:
36.
If the equalizing line on a differential pressure (D/P) flow detector is opened,.the flow detector indication will:
A.
increase slightly.
B.
decrease slightly.
C.
go to zero.
D.
not change.
QUESTION:
37.
Flow detectors (such as an orifice, flow nozzle, and venturi tube) measure flow rate using the principle that flow rate is:
DIRECTLY proportional to the differential pressure.
'A.
INVERSELY proportional to the differential pressure.
B.
DIRF.CTLY proportional to the square root of the differential pressure.
C.
INVERSELI proportional to the square root of the differential pressure.
D.
l FORM B Page 12 of 34 1
-i!---____________.
i
' PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS 'EKANIMATION t
FORM B I
QUESTION:
38.
The pressure differential between a reference leg and a variable leg is:
A.
DIRECTkY proportional to the height of the variable leg, i
B.
INVERSELY proportional to the height of the variable leg.
C.
DIRECTLY proportional to the density of the reference leg.
D.
INVERSELY proportional to the temperature of the reference leg.
QUESTION:
39.
If the reference leg of a differential pressure level indicator experiences high ambient temperature, indicated level will:
i A.
read less than actual level.
B.
read greater than actual level.
C.
equal the actual level.
t D.
slowly decrease to zero.
QUESTION:
40, i
l The output for a reference leg differential pressure level instrument will l
fail LQE as a result of:
A.
a break on the reference leg.
1 B.
a rupture of the diaphragm in the differential pressure cell.
C.
the reference leg flashing to steam.
L D.
a break on the variable leg.
FORM B Page 13 of 34
=
..,. - ~,.
,. = - - -. -,, -,,,,.,
7 PRESSURIZED WATER REAC1tNL CDIERIC FUNDAMENTALS EXAMINATION l
M)RN 2 QUEST 1ON: 41.
J A resistance temperature detoctor (RTD) operates on the principle that the j
change in electrical resistance of:
A.
two' dissimilar metals is PIRECTLY proportional to the temperature change measured at their junction.
j 1
B.
two. dissimilar metals is INVERSELY proportional to the temperature change 4
measured at their junction.
C.
c metal is PIRECTLY proportional to its change in temperature.
D.
a metal is INVERSELY proportional to its changs in temperature.
QUESTION: 42.
Two differential pressure level transmitters are installed in a large tank.
If transmitter I is calibrated at 200 degrees F and transmitter II is calibrated at 100 degrees F, then at 150 degrees F:
A.
transmitter I will read greater than transtsitter II.
B.
transmitter II will read greater than transmitter I.
C.
transmitter I and II will read the same.
D.
.it is impossible to predict how either transmitter will respond.
QUESTION: 43.
Scintillation detectors operate on the principle of:
r I
A.
photodisintegration.
B.
photokinesis.
C.
photomultiplicatiots.
D.
photoionization.
1.<
FORM B Page 14 of 34
a a
+
s..
PRESSURIZED WATER REAC1CR CDIERIC WNDAMENTALS EKAMINATION j
S FORM B QUESTION: 44 A BF3 proportional counter detects both neutrons and gammas. Which of the-following best describes the method used to eliminate the gamma contribution from the detector output?
A.
Two counters are used, one sensitive to neutron and gamma and the other sensitive to gamma only. The outputs are electrically opposed to cancel the gamma induced currents and yield a, neutron only signal for indication use.
B.
The BF3 proportional detector records neutron flux of sufficient intensity that the gamma signal is insignificant compared to the neutron signal and yields a neutron only signal for indication use.
(i O.
Gamma induced detector pulses are of insufficient width to generate a significant log level amplifier output. Neutron pulsos are the only ones with sufficient width to yield a neutron only signal for indication use.
D.
Neutron induced current pulses are significantly larger than those from gamma. The detector signal is applied to a circuit which filters out the smaller gamma pulses yielding a neutron only signal for indication use.
l' QUESTION:
45.
l The difference between the setpoint and the measured parameter in an automatic flow controller is called:
A.
- gain, i
B.
bias.
C.
feedback.
I D.
error.
QUESTION:
46.
A controller's output is typically insufficient to accurately drive a valve actuator. To overcome this problem, a control loop normally employs:
A.
a lead / lag unit.
B.
a regulator.
C.
a positioner.
D.
an amplifier unit.
FDRM B Page 15 of 34 l
b
PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION 70RM S j
QUESTION:
47.
Why must an operator pay particular attention to auto / manual valve controllers left in the manual mode?
A.
The manual valve control is usually not stable compared to the automatic mode.
B.
The valve position will no longer respond to changes in system parameters, t
C.
The controlled parametors vill no longer be controlled by the valve position..
D.
The valve can only be operated locally durin6 this time.
1 QUESTION:
48.
What precautions must be observed when transferring a valve controller from the automatic mode to manual mode of control?
A.
Ensure that the proper offset is established between the i
automatic mode and manual mode.
B.
Ensure that the valve controller output signals are mat".hed between automatic mode and manual mode.
C.
Ensure that the valve controller stabilises in the automatic mode before completely transferring to the manual mode of control.
D.
Ensure that the automatic valve controller signal is ine.reasing before transferring to manual mode of control.
QUESTION:
49.
An indication of centrifugal pump cavitation is:
A.
pump motor amps pegged high.
l B.
pump discharge pressure indicating zero.
1 C.
pump motor amps oscillating.
L D.
pump discharge pressure indicating shutoff head.
1 1
L 1
l' PORM B Page 16 of 34 I
7,.
FRESSURIZED WATER REACTOR CENERIC PVNDAMENTALS EXAMINATION PORM B l
QUESTION:
50.
]
The term " shutoff head" for a centrifugal pump indicates that it is pumping j
at:
1 A.
maximum capacity and minimum discharge head.-
B.
maximum capacity and maximum discharge head.
C.
minimum capacity and maximum discharge head.
D.
minimum capacity and minimum discharge head QUESTION:
51.
Operating a motor driven centrifugal pump for.$xtended periods of time with no flow through the pump will cause:
A.
pump failure from overspeed, i
B.
pump failure from overheating.
C.
motor failure from overspeed.
' D.
motor failure from overheating.
1 l
QUESTION:
52.
SHUTTING the discharge valve on an operating centrifugal pump will cause the y
MOTOR AMPS to and the pump DISCHARGE PRESSURE to A..
increase,-increase B.
decrease, increase C.
increase, decrease D.
decrease, decrease FORM B Page 17 of 34
La.
PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EKANINATION FORN 5 o-QUESTION:
53.
t
'If.the speed'of a positive displacement pump is increased, the available net 1
' positive suction head (NPSH) will and the probability of
' cavitation will 1
A.'
increase, increase q
B.
decrease, decrease C.
increase, decrease D.
. decrease, increase l
'I QUESTION:
54 Reactor coolant pump motor amps will if the rotor is LQGKED and-the motor: speci will if the rotor EHE&RA.
A.
Increase, increase Bi increase, decrease-
{
C.
decrease, increase D.-
decrease, decrease i
QUESTION:
55.
If the generator bearings on a motor generator overheat then:
D A.
the' generator voltage will increase.
I
~.+
B.
the generator windings will overheat.
l.
-i l
C.
the motor current will decrease.
j p
f D,
the motor windings will overheat.
.f b
l FORM B Page 18 of 34
7-
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'.' f l
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PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALE EIANIMATION n ;, s -
FORM B
>1
-1 56.
. QUESTION:
'If the speed'of a variable speed centrifugal pump is increased to cause pump j
flow rate to double, pump motor current will.
mA.-
remain constant.
j a
B.
' increase two. fold (double).
1 C.
increase four fold, e
increase eight fold.
'D.
lj
..'1 :
QUESTION:
57.
The starting current in an A.C. motor is significantly higher than the j
full load running current because:
A.
starting torque is lower than running torque, a
B..
starting' torque is higher than running torque.
C.
. rotor current during. start is higher than runnina current..
r D.
. rotor current during start is lower than running current.
QUESTION:
58.
"The' number of starts for an electric motor in a given period of time should be a
limited because:
l R,
A, overheating of the windings can occur.
l-L B.
excessive torque is generated during motor start.
r j-C.-
running current is much higher than starting current.
1l 1
D.
motors are normally started under full load conditions.
l 3
l>
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1 FORM B Page 19 of 34 i
4;.
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.L e ronN a PR6.SSURIEED WATER REAC1tlR CENERIC FUNDMIENTALA IIANIMATICII l
Lo.
' QUt$ TION:
59.
j i
$evere attess in a mechanical component, induced by a sudden, uraquelly j
distributed temp 2rature reduction is a description of:
l A.
heat stress, l
F F B.
tharsal shock.
j C.
thermal strain.
e D.
heat strain.
]
t
[
QUESTION: 60.
)
J Tube fouling in a heat exchanger causes hi a transfer to decrease by:
1 A.
reducing fluid volonity on the shell side of the exchanger.
M.
increasing flow rate through the tube side of the exchanger.
C.
reducing the overall (total) heat transfer coefficient.
D.
increasing the overall (total) heat transfer coefficient.
QUESTION: 61.
Borated water is flowing through the tubes of a heat exchanger being cooled by fresh water.
The shel; eide pressure is less than tube side pressure. What will occur as a result of a tube failure?
A.
Depletion of borated water inventory.
j B.
Depletion of cooling water inventory.
l C.
Dilution of the borated water system.
D.
Shell pressure will decrease.
i L
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l FORK B Page 20 of 34 l'
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PitES$URIZED WATER REACTOR CFWElRIC NJtENTAIJ EKAMINATION FORM B QUESTION: 02.
What is the reason for bypassing a demineralizer due to high temperature?
{
A.
Resins expand and restrict flow thrvugh the demineralizer.
[
B.
The domineralizer decontamination factor is dramatically increased.
C.
Organic compounds used as resins will decompose.
[
D.
The creation of preferential flowpath through the domineralizer will j
occur.
QUESTION:
63.
In the event of a system crud burst, what adverse effect does the crud burst have on domineralizer operation?
j A.
Increases pressure drop across domineralizer B.
Increases flow rate through demineralizer C.
Increases demineralizer outlet conductivity j
i D.
Increases deniaeralizer inlet pH QUESTION:
64 Boron concentration in the reactor (primary) coolant system has been de.
creasing steadily at approximately 10 ppa per hour while using the deborating demineralizer. After several hours, the rate decreases to 2 ppe per hour.
i-What is a possible cause for the change in deboration rate?
l i
A.
Temperature of the coo 16.t passing through the domineralizer has decreased.
B.
pit of the coolant has increased significantly, i
i l
C.
Flow through the deborating resins has increased sharply.
L D.
Deborating resins have become boron saturated.
I I
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FORM B Page 21 of 34
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L
. P81SSURIEED CATR REACTOR CENERIC FWDAMENTALS EXAMINATION FORM B QUESTION:
65.
To de energine a component and its associated control and indication circuits.
the component circuit breaksr should be:
I A.
racked in and tagged in open position.
B.
racked in and tagged in closed position.
r C.
racked out and tagged in racked.out position.
D.
in the test position and tagged in tesc.
l t
i QUESTION:
66.
To ensure reliable local breaker indication is bein5 provided the r
must be reset af ter breaker operation.
A.
OPEN/ CLOSED mechanical flag l
B.
OPEN/ CLOSED indicating lights C.
Overcurrent trip flag D.
Spring CHARCE/DISCRARGE flag i
QUESTION: '67, i
A circuit breaker thermal overload device:
{
A.
compares actual current to a fixed overcurrent setpoint that is equated
[
to temperature and actuates a trip relay.
i i
B.
when subjected to high current, overheats and actuates a circuit.
interrupting device.
C.
senses operating equipment temperature and trips protective circuits at
(
preset limits.
\\.
(
D.
is an induction coil that produces a secondary current proportional to l
the primary current.
t l
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FORM B Page 22 of 34 i
PRESSORIZED WATER REACTOR CENERIC WNDAMENTA13 EKANINATION POP.M $
i l
l QUESTION:
68.
Loss of circuit breaker control power will cause:
1 A.
breaker line voltage to be zero regardless of actual breaker position.
l B.
the remote breaker position to indicate closed regardless of actual
)
1 breaker position.
1 C.
inability to operate the breaker locally and remotely.
D.
failure of the close spring to charge following local tripping of the breaker.
QUESTION:
69.
If a de energized bus is not unloaded prior to cloring the output breaker of a three. phase generator onto the bus, then:
A.
an overvoltage condition will occur on the bus.
B.
an overcurrent condition will occur on the generator.
C.
an overvoltage condition will occur between generator phases.
D.
generator undervoltage relay actuation vill occur.
QUESTION:
70.
Which of the following statements is correct concerning the use of disconnect switches?
A, Disconnects should be limited to normal load current interruption.
B.
Disconnects may be used to isolate transformers in an unloaded network.
s C.
Disconnects are similar to oil circuit breakers, but are manually operated.
I D.
Dinconnects must be closed with caution when under load bec:use of possible arcing.
l
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FORM a Page 23 of 34 l
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'FRESSURIZED WATLA REACTOR CENEk1C FUNDAMENTA1A EEANIMATION y0mg a l
QUESTION:
71.
l Closing a generator output breaker with the generator frequency much less than grid frequency will cause the generator to trip on:
A.
reverse p(ver.
1 B.
overvoltage.
{
-l C.
)
D, overspeed.
i i
i l
QUESTION:
72.
{
The operator has just pulled control rods and chan5ed the effective multipli.
[
cation factor (Keff) from 0,998 to 1.002.
The reactor is:
A.
prompt critical 3.
supercritical C.
exactly critical l
t D.
suberitical i
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t (L
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1 1
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FORM B Page 24 of 34
PRESSURIED WATR REACTOR CENRIC FWDAMENTALS ERANIMATION PORN B t-QUESTION:
73.
i The ratio of the number of neutrons in one generation to the number of neutrons in the previous generation is the:
A.
effective multiplication factor B.
fast fission factor C.
neutron non leakage factor D.
neutron reproduction factor QUESTION:
74.
Reactivity is defined as the:
A.
fractional change in neutron population per generation.
B.
number of neutrons by which neutron population changes per generation.
C.
rate of change of _ reactor power in neutrons per second.
D, change in the number of neutrons per second that causes a fission event.
QUESTION:
75.
A given amount of positive reactivity is added to a critical reactor in the source (startup) range. The amount added is less than the average effective delayed neutron fraction. Which of the following will have a significant effect on the magnitude of the stable startup rate achieved for this addition?
A.
Prompt neutron lifetime B.
Fuel temperature coefficient C.
Average effective decay constant D.
Moderator temperature coefficient l
l l
I 1
l l
PokN B Page 25 of 34
I.
PRESStRIEED WATER REACTOR CENERIC FUNDAMENTALS ERANIMATION I
FORM B i
i#
l QUESTION:
76.
I Over core life the production of plutontua isotopes with delayed neutron fractions than uranium delayed neutron fractions will cause I
reactor power transients to be near the end of core life.
J A.
less, fanter B.
less, slower C.
greater, faster i
D.
greater, slower
\\
QUESTION:
77.
t i
An installed neutron source:
A.
maintains the production of neutrons high enough to allow the reactor to
}
achieve criticality, i
B.
provides a means to allow reactivity changes to' occur in a subcritical reactor.
C.
generates a sufficient neutron population to start the fission process and initiate suberitical multiplication.
1 D.
provides a neutron level that is detectable on the source range nuclear l
instrumentation.
l l-i QUESTION:
78.
Why does increasing reacter coolant boron concentration cause the moderator temperature coefficient to become iees negative?
1 A.
Reactor coolant temperature increases result in a larger increase in the l
thermal utilization factor, g
i l
B.
Reactor coolant temperature increases result in an increase in the resonance escape probability.
t l'
C.
Reactor coolant temperature increases result in an inctaase in the total i
l-non leakage probability, D.
The change in resonance escape probability dominates the change in the thermal utilization factor.
f l'
FORM B Page 26 of 34 I
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PILESSURIZED WATRIL ILEACTOIt CENERIC FUNDM(ENTALS EKAMINATICII FORM S j
)
QUESTION:
79.
j Why does the fuel temperature (Doppler) coefficient becomes less negative at higher fuel temperatures?
i
)
A.
As reactor power increases, the rate of increase in the fuel temperature j
diminishe:s.
5.
Neutrons penetrate deeper into the fuel, resultin5 in an increase in the l
fast fission factor.
C.
The amount of self. shielding increases, resulting in less neutron I
absorption by the inner fuel.
{
D.
The amount of Doppler broadening per degree change in fuel temperature f
diminishes.
t QUESTION:
80.
i A reactivity coefficient measures change while a reactivity defect (deficit) measures a change in reactivity due to a change in the measured parameter.
A.
an integrated, total 3.
a rate of, differential C.
a differential, total D.
a total, differential l
l L
QUESTION:
81.
[
During power operation, while changing power level, core reactivity is affected most quickly by:
A.
boron concentration adjustments.
B.
power defect (deficit).
C.
D.
fuel depletion.
l l
FORM B page 27 of 34
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(
P9J.SSURitED WATER REACTOR CENERIC PVNDAMENTALS EXAMINATION FORM B QUESTION:
82, i
i As moderator temperature increases, the magnitude of differential rod (CEA) worth increases because:
A.
decreased moderator density causes more neutron leakage out of the cere.
]
B.
moderator temperature coefficient decreases, causing decreased f
competition, t
C.
fuel temperature increases, decreasing neutron absorption in fuel, r
D.
decreased moderator density increases neutron migration length.
i QUESTION:
83.
Control rod (CEA) bank overlap:
A.
provides a more uniform differential rod (CEA) vorth and axial flux distribution.
r B.
provides a more unifora differential rod (CEA) worth and allows dampening of Xenon induced flux escillations.
C.
ensures that all rods (CEAs) remain within the allowable tolerance i
between their individus1 position indicators and their group counters and i
ensures rod (CEA) insertion limits are not exceeded.
D.
ensures that all rods (CEAs) remain within their allowable toleter ce between individual position indicators and their group counters u.d provides a more uniform axial flux distribution.
l t
QUESTION:
84.
J The basis for the maximum power density (kw/f t) power linit is to:
A.
prevent fuel clad melt.
B.
prevent fuel pellet melt.
C.
limit bulk coolant temperature.
I D.
prevent nucleate boiling.
f FORM B Page 28 of 34
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PRESSURIEED WATER REACTOR CENERIC WNDAMENTA13 EKANIMATION FORM S i
QUESTION:
85.
j 1
The control rod insertion limits are power level dependent because the
)
magnitude of:
i A.
control rod worth decreases as power increases.
J B.
power defect increases as power increases, j
C.
Doppler (fuel temperature) coefficient decreases as power increases.
D.
moderator temperature coefficient itecteases as power increases.
l QUESTION:
86.
Fission products that have substantial neutron capture cross sections are:
A.
excited fission products, i
i B.
fission product daughter, C.
radioactive fission products.
D.
fission product poisons.
QUESTION:
87.
Following a reactor trip from sustained high power operation, Xenon.135 concentration in the reactor will:
A.
decrease because Xenon is produced directly from fission.
B.
increase due to the decay of Iodine already in the core.
C.
remain the same because the decay of Iodine and Xenon balance each other out.
D.
decrease immediately, then slowly increase due to the differences in the half lives of Iodine and Xenon.
M FORM B Page 29 of 34
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L PRESSURIEED WATER REAC1tlR CENERIC FUNDMIENTA1A EEANIMATION i
?
o PORM S l
h QDESTICA:
88.
I Following a reactor trip from sustained high power operation, the major Xenon t
135 removal process is:
A.
ion exchange, j
B.
beta decay.
f C.
neutron capture, j
i D.
alpha decay.
I QUESTION: 89.
A reactor has been operating at 50 percent power for 7 days when power is i
ramped to 100 percent over a four hour period. The new equilibrium Xenon value will:
A.
be twice the 50 percent value.
B.
be less than twice the 50 percent value, i
C.
be more than twice the 50 percent value.
i D.
remain the same since it is independent of power, j
I l
QUESTION: 90, i
Slow changes in axial power distribution in a reactor that has operated at a steady state power for a long time can be caused by:
A.
Xenon peaking.
B.
Xenon override.
C.
Xenon burnup.
D.
Xenon oscillation.
1 1
i PORN B Page 30 of 34
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RES$URIEED WATEL REAC'NE CRJf5t!C FUNDAK5FTA1A ERANINATION L'
FoaN B p'l J
QUESTION:
91.
A reactor that has been operating at rated power for about two weeks reduces power to 50 percent. Xe 135 will reach a new equilibrium condition in hours.
j A..
8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 4
B.
20 to 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> C.
30 to 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> D.
40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> i
i I
i QUESTION: 92.
}
The reactor is near the end of its operating cycle.
In order to stay critical, power and temperature have been allowed to 'coastdown." Why is boron no longer used to compensate for fuel depletion?
A.
Boron concentration approaches zero and requires excessive amounts of water to dilute.
B.
The differential boron worth has decreased below its useable point.
C.
The boron in the coolant has been depleted due to neutron absorption.
D.
"Coastdown" is preferred due to fuel conditioning limitations.
5 QUESTION:
93.
i While withdrawing control rods during an approach to criticality, the count rate doubles. What will occur if the same amount of reactivity that caused the first doubling is added again?
i l
A.
Count rate will increase slightly.
B.
Count rate will double.
l C.
The reactcr will remain suberitical.
I t
D.
The reactor will be critical or slightly supercritical.
l' i
1 1
FORM B Page 31 of 34 i
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PRESSURIEED WATER REACTOR CENERIC FUNDMGNTA1A ERANINATICII c
roRN i
h QUESTION:. 94 I
I 6
In a reactor with a source, a non. changing neutron flux over a few minutes is indicative of criticality or:
l A.
tha point of adding heat.
(
B.
supercriticality, j
)
C.
suberiticality.
D.
equilibrium suberitical count rate.
QUESTION:
95.
At EOL, critical rod (CEA) position has been calculated for a reactor startup four hours after a trip from 100 percent power equilibrium conditions. The actual critical rod (CEA) position will be IDWER than the predicted critical j
rod (CEA) position if:
A.
the startup is delayed until eight hours after the trip.
f I
B, the steam dump pressure setpoint is lowered by 100 psi prior to reactor i
startup.
j C.
actual boron concentration is 10 ppa more than t.he assumed boron f
concentration.
'D.
one control rod (CLA) remains fully inserted during the approach to criticality.
t QUESTION:
96.
[
With keff - 0.985, how much reactivity must be added to make the reactor j
critical?
l A.
1,480 pcm (1.484 delta.k/k) i B.
1,500 pcm (1.50% delta k/k)
C.
1,520 pcm (1.52% delta k/k)
D.
1,540 pcm (1.54% delta k/k) r FORM B Page 32 of 34
(
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PRESS'3L1EED WATER REACTOR GENRIC FUNDAMENTALS EIAMINATICII 0
FORM B I
)J QUESTION:
97.
i l
I If, during a reactor startup, the startup rate is constant and positive without any further reactivity addition, then the reactor is:
.j A.
critical.
B.
supercritical.
l C.
suberitical.
D.
prompt critical.
1 i
QUESTION:
98.
l 1
Civen a critical reactor operating below the point of adding heat, what reactivity effects are associated with reaching the point of adding heat?
A.
There are no reactivity effects since the reactor is critical.
{
B.
The increase in fuel temperature will begin to create a positive I
reactivity effect.
C.
The decrease in fuel temperature will begin to create a negative reactivity effect.
t D.
The increase in fuel temperature will begin to create a negative reactivity effect.
QUESTION:
99.
Shortly after a reactor trip, reactor power indicates 0.5 percent where a l
stable negative SUR is attained.
Reactor power will be reduced to 0.05 percent in approximately seconds.
A.
360 B.
270 C.
180 D.
90 k
b i
FORM B Page 33 of 34 i
\\;79 %t
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PILES $ Ult 1EED WATDL REACTClt CDfDLIC IVNDMENTALB IXAMINATICII PoltM &
QUESTION:
100.
The major reason boron is used in a reactor is to permit:
1 A.
a reduction in the shutdown margin.
B.
an increase in the amount of control rods (CE.As) installed.
C.
an increase in core life.
D.
a reduction in the effect of resonance capture, i
r i
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F0ltM B Page 34 of 34 l
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