ML19324B702
| ML19324B702 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/01/1989 |
| From: | Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mcginnis D DUKE POWER CO. |
| References | |
| NUDOCS 8911080048 | |
| Download: ML19324B702 (78) | |
Text
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J We,17GD ST AfIS
' #*# p t M 4 NUCLE AH RECULATCRY COWHel210N
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to: sow si I~
101lAAmitif A ST48Lf.N.W.
I ATLANT A.elomol A 39328 k....
November 1, 1989 Docket Nos. 50 369 and 50 370 i
Duke Power Company ATTN: Mr. D. M. McGinnis, Director McGuire Operations Training Training and Technology Center Route 4, Box 531 Huntersville,NC 20078 GENTLEMEN On October 4.1989, the NRC administered the Generic Fundamentals Examination Section (GFES) of the written operator licensing examination to employees of your facility.
Enclosed with this letter are copies of both foms of the examination < ncluding 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 Conniission's Regulations, a copy of this letter and Enclosures 1 and 2 will be placed in the NRC's Public Document 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.
)
f Sincerel.
'4d. / M
/ Operations Branch
" ^ '" ' '"
Division of Reactor Safety
Enclosures:
1.
Examination Forz 'A' with Answers 2.
Examination Fors 'B' with Answers 3.
Examination Results Sunsnary for Facility 4.
Copies of Candidates Individual Answer Sheets l
Ofol
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891108004e 391101 PDR ADOCK 05000369 l
V PNU m
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ANSWER KEY PWR GFE (FORM'A) 1.
C.
26.
A.
51.
D.-
76.
B.
2.
D.
27.
D.
52.
C.
77.
D.
i 3.
A.
?. 8.
D.
53.
B.
78.
D.
4.
D.
M 54.
D.
79.
B.
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.
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.
h 39.
B.
64.
A.
89.
B.
15.
C.
40.
D.
65.
D.
90.
D.
16.
D.
41.
B.
66.
D.
91.
D.
17.
D.
42.
B.
67.
B.
92.
A.
18.
C.
43.
A.
68.
C.
03.
A.
19.
B.
44.
B.
69.
B.
94.
B.
20.
B.
4 5..
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.
j f
&"usurized Water Reactor Generic Fundamentals Examination
'nistered October 4,1989.
Questions 14, 39 and 56 e n. deleted.
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ANSWER KEY PWR GFE (FORM B) 1.
D.
26.
A.
51.
B.
76.
A.
2.
A.
27.
A.
52.
B.
77.
D.
l 3.
D.
28.
D.
53.
D.
78.
A.
4.
B.
29.
C.
54.
A.
79.
D.
5.
D.
3 0..
D.
55.
D.
80.
C.
1 6.
D.
31.
A.
56.
D.
81.
B.
7.
B.
32.
D.
!?.
7.
82.
D.
8.
C.
33.
B.
58.
A.
83.
A.
9.
C.
34.
B.
59.
B.
M 10.
C.
35.
D.
60.
C.
85.
B.
11.
A.
36.
C.
61.
A.
86.
D.
12.
D.
37.
C.
62.
C.
87.
B.
13.
B.
38.
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.
C.
m 67.
B.
92.
A.
18.
D.
43.
C.
68.
D.
93.
D.
19.
D.
44.
D.
69.
B.
94.
D.
20.
A.
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.
B.
49.
C.
74.
A.
99.
C.
I 25.
B.
50.
C.
75.
C.
100.
C.
l Pressurized Water Reactor Generic Fundamentals Examination administered October 4, 1989. Questions 42, 57 and 84 were 1
deleted.
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f is UNITED STATES NUCLEAR RECUIATORY COMMISSION PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION Please Print:
Nr.me :
Facility:
ID Number:
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 1
P COMPONENTS 1 - 43 REACTOR THEORY 44 72 THERMODYNAMICS 73 100 TOTALS 100 l
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All work done on this examination is my own.
I have neither given nor j
received aid.
Candidate's Signature 1
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I O
t RULES AND CUIDELINES FOR THE GENERIC 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.
(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 narked 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.
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CENRIC FUNDAMETA1A EEAMINATION SECTION BQUATIONS AND CONVERSIONS HANDOITT SHEET EDUATIONS j
j Cycle Efficiency Nat Work (out) 6
- ac AT p
Energy (in) 6 A Ah SCR S/(1. K,gg) l
=
6 UA AT CRg (1. K,gg)g - CR2 (1
- Koff)2 SUR - 26.06/r M
1/(1. K,gg)
CR /CR g
0 26.06 (A,gg p)
(1. K,gg)0 SUR =
M
=
,,(p. p)
(1. K,gg)g SLR(t)
P,10 SDM P
(1 K,gg)/K,gg
=
P,e(#/#)
W 5 P
Pwr
=
g e
1*/(p * #)
(1/p)+[(3.p)/A,gg]
f' p
f
=
p (K,gg. 1)/K,gg 1*
1 x 10 5 seconds
- I p
AK,gg/K,gg A,gg - 0.1 seconds i
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CONVERSIONS 10 1 Curie 3.7 x 10 dps 1 kg 2.21 lba 3
0 1 hp 2.54 x 10 BTU /hr 1 Mw 3.41 x 10 BTU /hr L
1 BTU 778 ft-lbf
- F 9/5 *C + 32 l
lt
- C 5/9 (*F. 32) l l
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PRESSURIZED WATER REACTOR CDIERIC MJNDAMENTALS EKAMINATION FORM A 8
' QUESTION:
1.-
'The primary purpose of a pressure relief valve is to:
A.
maintain system flow.
B.
maintain system pressure.
C.
maintain system integrity.
D.
meintain system temperature.
QUESTION:
2.
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:
3.
The function of e. valve backseat is to:
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 of valve repacking.
C.
provide a backup means of flow isolation in the event of primary seat leakage.
D.
provide a backup means of flow isolation in the event of a pipe break.
FORM A Page 1 of 35
PRESSURIZED WATER REACTOR CENERIC PVNDAMENTALS EKAMINATION FORM A QUESTION:
4.-
After manually positioning a motor operated valve, how is the valve actuator re engcged?
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 D.
Actuation of the valve actuator motor in either the open or close direction 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.
C.
in the open direction until flow sounds are heard, then close the valve using manual force.
D.
in the closed direction until it stops, then close it an additional one half turn using normal force.
QUESTION:
6.
Density compensation is used in flow instruments to change to A.
mass flow rate, volumetric flow rate B.
volumetric flow rate, mass flow rate C.
fluid pressure, volumetric flow rate D.
differential pressure, mass flow rate 1
FORM A Page 2 of 35
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PRESSURIZED WATER REACTOR CENERIC MINDAMENTALS EXAMINATION I'n FORM A
[g '
QUESTION:
7.
t E
LIf the liquid flowing through a liquid flow rate sensor contains entrained voids (Eas or steam), indicated flow rate will be:
,4 A.
erroneously high.
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B.
erroneously low.
C.
unaffected, i
D.
fluctuating.
QUESTION:
8.
If the equalizing line on a differential pressure (D/P) flow detector la g
opened, the flow detector indication will:
A.
increase slightly.
B.
decrease slightly.
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C.
go to zero.
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D.
not change.
l QUESTION:
9.
Flow detectors (such as an orifice, flow nozzle, and venturi tube) measure
' flow rate using the principle that flow rate is:
A.
DIRECTLY proportional to the differential pressure.
B.
INVERSELY proportional to the differential pressure.
C.
DIRECTLY proportional to the square root of the differential pressure.
D.
INVERSELY proportional to the square root of the differential pressure.
i FORM A Page 3 of 35 3
s PRESSURIZED WATER REACTOR CENERIC WNDAMENTALS EXAMINATION
.o QUESTION:
10.
The pressure differential between a reference leg and a variable leg is:
A.
DIRECTLY proportional to the height of the variable leg.
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:
11.
If the reference leg of a differential pressure level indicator experiences high ambient temperature, indicated 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.
The level indication for a reference leg differential pressure level instrument will fail 1 3 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.
D.
a break on the variable leg.
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FORM A Page 4 of 35
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'o PRESSURIZED WATER REAC1DR CENERIC PVNDAMENTALS EXAMINATION i
PORM 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 measured at their junction.
B.
two dissimilar metals is INVERSELY proportional to the temperature change
[
measured at their junction.
i C.
a metal is DIREC10Y proportional to its change in temperature.
D.
a metal is INVERSELY proportional to its change in temperature, i
QUESTION:
14.
Two differential pressure level transmitters are installed in a large tank.
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.
QUESTION:
15.
Scintillation detectors operate on the principle of:
A.
photodisintegration.
B.
photokinesis.
C.
photomultiplication.
D.
photoionization.
FORM A Page 5 of 35
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PRESSURIZED WATER REACMR CENERIC WNDAMENTALS EXANINATION FORN A L
QUESTION:
16.
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.
C.
Camma induced detector pulses are of insufficient width to generate a significant log level amplifier output.
Neutron pulses 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.
QUESTION:
17.
The difference between the setpoint and the measure 6 parameter in an automatic flow controller is called:
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A.
gain.
B.
bias.
C.
feedback.
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D.
- error, l
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QUESTION:
18.
A controller's output is typically insufficient to accurately drive a valve actuator. To overcome this problem, a control loop normally employs:
l A.
A lead /la6 unit.
B.
a regulator.
C.
a positioner.
D.
an amplifier unit.
FORK A Page 6 of 35
' PRESSURIZED WATER REACTOR CENEFJC FUNDAMENTA13 EXAMINATION PORK A QUESTION:
19.
Why must sn 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.
C.
The controlled perameters 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 che proper offset is established between the automatic mode and manual mode.
B.
Ensure that the valve controller output signals are matched between automatic 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.
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QUFSTION:
21.
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An indication of centrifugal pump cavitation is:
A.
pump motor amps pegged high, 1
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pump discharge pressure indicating zero.
C.
pump motor amps oscillating.
D.
pump discharge pressure indicating shutoff head.
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l FORM A Page 7 of 35 i
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h PRESSURIZED WATER REAC1TIR CENERIC PVNDAMENTAIA EXANINATION h
FORM A QUESTION:
22.
1 The term " shutoff head" for a centrifugal pump indicates that it is pumping L
at:.
A.
maximum capacity and minimum discharge head.
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.B.
' maximum capacity.and maximum discharge head.
C.
minimum capacity and maximum discharge head.
D.
minimum capacity and minimum discharge head.
QUESTION:
23.
Operating a motor driven centrifugal pump for extended periods of time with no flow through the pump will cause:
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A.
pump failure from overspeed.
B.
pump failure from overheating.
C.
motor failure from overspeed, l-j' D.
motor failure from overheating, l
L QUESTION:
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l SKUTTING the discharge valve on an operating centrifugal pump will cause the L
ltOTOR AMPS to and the pump DISCHARCE PRESSURE to
.A.
increase, increase B.
decrease, increase C.
increase, decrease l
D.
decrease, decrease i
FORM A Page 8 of 35
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PRESSURIZED WATER REACTOR CENERIC FUNDAMENTAIE EXAMINATION PORM A QUESTION:
25, i
If the speed of a positive displacement pump is increased, the available net positive suction head (NPSH) will and the probability of cavitation will
' ncrease, increase i
A, B.
decrease, decrease C.
increase, decrease l
D.
decrease, increase QUESTION:
26.
Reactor coolant pump motor amps will
_ if the rotor in LO2EED and the motor speed will if the rotor SHEARS.
A.
increase, increase B.
increase, decrease C.
decrease, increase D.
decrease, decrease t
QUESTION:
27.
If th'e generator bearings on a motor generator overheat then:
A.
the generator voltage will increase.
l B.
the generator windings will overheat.
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C.
the motor current will decrease.
D.
the motor windings will overheat.
.r FORM A Page 9 of 35
I PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA13 EKAMINATION j
FORM A
' QUESTION:
28.
If the speed of a variable speed centrifugal pump is increaset to cause pump j
-flow rate to double, pump motor current'will:
A.
remain constant.
?
B.
increase two fold (double).
C.
increase four-fold.
D.
increase eight fold.
l QUESTION:
29.
The starting current in an A.C. motor is significantly higher than the full load running current because:
A.
starting torque is lower than running torque.
B.
starting torque is higher than running torque.
C.
rotor current during start is higher than running current.
D.
rotor current during start is lower than running current.
l QUESTION:
30.
The number of starts for an electric motor in a given period of time should be
. limited because:
A.
overheating of the windings can occur.
L B.
excessive torque is generated during motor start.
l C.
running current is much higher than starting current.
D.
motors are normally started under full load conditions.
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FORM A Page 10 of 35 l
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1 PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION j
i PORN A g
-QUESTION:
31.
Severe stress in a mechanical component, induced by a sudden, unequally distributed temperature reduction is a description of:
A.'
heat stress.
B.
thermal shock.
C..
thermal strain.
-D.
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.
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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.
C.
Dilution of the borated water system.
D.
Shell pressure will decrease.
I FORM A Page 11 of 35
PRESSURIZED WATER REACTOR GENERIC WNDAMENTAIE EXAMINATION FORM A QUESTION:
34 What is the reason for bypassing a desineralizer due to high temperature?
A.
Resins expand and restrict flow through the demineralizer.
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B.
The demineralizer decontamination factor is dramatically increased.
C.
Organic compounds used as resins will decompose, D.
The creation of preferential flowpath through the demineralizer will occur.
QUESTION:
35.
In the event of a system crud burst, what adverse effect does the crud burst have on demineralizer operation?
A.
Increases pressure drop across demineralizer B.
Incr,ases flow rate through demineralizer C.
Increases demineralizer outlet conductivity D.
Increases demineralizer inlet pH QUESTION:
36.
Boron concentration in the reactor (primary) coolant system has been decreasing stecdily at approximately 10 ppm per hour while using the deborating demineralizer. After several hours, the rate decreases to 2 ppm j.
per hour. What is a possible cause for the change in deboration rate?
A.
Temperature of the coolant passing through the demineralizer has decreased.
B.
pH of the coolant has increased si nificantly.
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C.
Flow through the deborating resins has increased sharply.
D.
Deborating resins have become boron saturated.
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FORM A Page 12 of 35 l
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- PRES $URIZ6.D WATER REACTOR CENERIC WNDAMENTALS EKMilNATION
- 3.
FORM A 4
. QUESTION:
37.
1 Te de energite a component and its associated control and indication circuits,
/the' component circuit breaker should be:
l
'A.
racked in and tagged in open position.
If B.'
. racked in and tagged in closed position.
C.
racked out and tagged in racked out position.
D.
in the test position and tagged in test.
QUESTION:
38.
To. ensure reliable local breaker indication is being provided the must be reset after breaker operation.
l A.
OPEN/ CLOSED mechanical flag i
B.
0 PEN / CLOSED indicating lights i
C.
Overcurrent trip flag D.
Spring CHARGE / DISCHARGE flag L
QUESTION:
39..
1 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.
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'B.
when subjected to high current, overheats and actuates a circuit interrupting device.
1 C.
senses operating equipment temperature and trips protective circuits at preset limits.
1
[
D.
is an induction coil that produces a secondary current proportional to I
the primary current.
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l l-FORM A Page 13 of 35 l
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PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA13 EXAMINATION FORM A QUESTION:- 40.
Loss of circuit breaker ~ control power will cause:
A.
breakor line voltage to be zero regardless of actual breaker position.
B.
the remote breaker position to indicate closed regardless of actual breaker position.
C.
inability to operate the breaker locally and remotely.
D.
failure of the close spring to charge following local tripping of the breaker.
QUESTION:
41.
If c 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.
B.
an overcurrent condition will occur on the generator.
C.
an overvoltage condition will occur between generator phases.
D.
generator undervoltage relay actuation will occur.
QUESTION:
42.
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 iaolate transformers in an unloaded network, l
C.
Disconnects are similar to oil circuit breakers, but are manually operated.
L D.
Disconnects must be closed with caution when under load because of possible arcing.
l L
i l
l FORM A Page 14 of 35
(
i.
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PRESS 131 ZED WATER REAC'It)R CENERIC WNDAMDrrA13 EKAMINATION FORM A s
I QUESTION:
43.
Closing a generator _ output breaker'with the generator frequency much less than grid frequency will cause the generator to trip on.
A.
reverse power.
t B.
'overvoltage.
C, overcurrent.
D.
QUESTION:
44.
The operator has just pulled control rods and changed the effective multipli-cation factor (K,ff) from 0.998 to 1.002.
The reactor is:
A.
prompt cri?.ical B.
supercritical i
C.
exactly critical D.
suberitical-L 1
l i
l' l
l 1
l FORM A Page 15 of 35 l;
11 $.
a FRESSURIZED WATER REACTOR CENERIC FUNDAMENTA13 EXAMINATION 70RM A j
p y, QUESTION:
45.
l' 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 i
D.
neutron reprcduction factor QUESTION:
46.
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 avent.
QUESTION:- 47.
A given amount of positive reactivity is added to a critical reactor in the i
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?
L' A.
Prompt neutron lifetime l
r B.
Fuel temperature coefficient C.
Average effective decay constant D.
Moderator temperature coefficient l
l^
1 1
FORM A Page 16 of 35
.c 1
L PRESSURIZED WATER REACTT)R CENERIC FUNDAMENTALS EXAMINATION FORN A l
i QUESTION:
~48.
j Over core' life the production of plutonium isotopes with delayed neutron fractions than uranium delayed neutron fractions will cause reactor power transients to be near the end of core life.
A.
~less, faster B.
less, slower C.
greater., faster D.
greater, slower t
QUESTION:
49.
An installed neutron source:
A.
maintains the production of neutrons high enough to allow the retctor to achieve criticality.
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.
D.
provides a neutron level that is detectable on the source range nuclear instrumentation..
QUESTION:
$0.
Why does increasing reactor.oolant boron concentration cause the moderator temperature coefficient to become less negative?
A.
Reactor coolant temperature increases result in a larger increase in the thermal utilization factor.
B.
Reactor coolant temperature increases result in an increase in the rcsonance escape probability.
C.
Reactor coolant temperature increases result in an increase in the total non leakage probability.
D.
The change in resonance escape proLability dominates the change in the thermal utilization factor.
FORM A Page 17 of 35
r s'*
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r PRESSURIZED WATER REACTOk CENERIC FUNDAMENTALS EKANINATION FORM A j-y
-QUESTION:
51.
Why does the fuel temperature (Doppler) coefficient becomes less negative at higher fuel temperatures?
A.
As reactor power increases, the rate of increase in the fuel temperature diminishes.
B.
Neutrons penetrate deeper into the fuel, resulting in an increase in the fast fission factor.
C.
The amount of self-shielding increases, resulting in less neutron absorption by the inner fuel.
D.
The amount of Doppler broadening per degree change in fuel temperature-diminishes.
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.
A.
An integrated, total B.
A rate of, differential
(
C.
A differential, total l
D.
A total, differential QUESTION: 53.
During power operation, while changing power level, core reactivity is l.
affected most quickly by:
L I
A.
boron concentration adjustments.
B.
power defect (deficit).
1 L
C.
D.
fuel depletion.
ll l
l l
FORM A Page 18 of 35 l
l
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o 1
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PRESSURIZED WATER REACTOR CENERIC ITNDAMENTALS EKAMINATION
,l F
FORN A QUESTION:
54.
As moderscor temperature increases, the magnitude of differential rod (CEA) worth increases because:
A.
decreased moderator density causes more neutron leakage out of the core.
B.
moderator temperature coefficient decreases, causing decreased competition.
C.
fuel temperature increases, decreasing neutron absorption in fuel.
D.
decreased moderator density increases neutron migration length.
QUESTION:
55.
Control rod (CEA) bank overlap:
provides a more uniform differential rod (CEA) worth 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 betweer their individual position indicators and their group counters and to ensure rod (CEA) insertion limits are not exceeded.
l 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:
56.
5 The basis 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.
l FORM A Page 19 of 35
i I
PRESSURIZED WATER REACTOR CENERIC FUNDAMDrTALS EXAMINATION FORM A QUESTION:
57, i
The control rod insertion limits are power level dependent because the magnitude of:
A.
contro). rod worth decreases as power increases.
B.
power defect increases as power increases.
C..
Doppler (fuel temperature) coefficient decreases as power increases.
D.
moderator temperature coefficient increases as power increases.
QUESTION:
58.
Fission products that have substantial neutron capture cross sections are:
A.
excited fission products.
B.
fission product daughter.
C.
radioactive fission products.
D.
fission product poisons.
QUESTION:
59.
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.
FORM A Page 20 of 35
PRESSURIZED WATER REAC't0R CENERIC MINDAMENTA1A EKAN1 NATION' 6
FORM A j
QUESTION:
60.
l i
Following a reactor trip from sustained high power operation, the major
]
Xenon.135 removal process is:
i i
A.
ion exchange, j
B.
beta decay.
C.
neutron capture.
P D.
alpha decay, i
1 QUESTION:
61.
A reactor has been operating at 50 percent power for 7 days when power is 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.
C.-
be more than twice the 50 percent value.
D.
remain the same since'it is independent of power.
r QUESTION:
62.
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.
4 B.
Xenon override.
C.
Xenon burnup.
D.
Xenon oscillation.
FORM A Page 21 of 35
-e 1.
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4
co FRESSURIZED WATER REACTOR CENERIC FUNDAMENTAIM EKAMINATION FORN A QUESTION:
63.
h 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 /> i
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 /> t
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 again?
l A.
Count rate will increase slightly, B.
Count rate will double.
C.
The reactor will remain suberitical.
I D.
The reactor will be critical or slightly supercritical.
1' l
l 1.
FORN A Page 22 of 35
rt ; -
i L.
. PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA!E EXAMINATION l.,
FORM A QUESTION:
66.
i b.
l' In a reactor with a source, a non changin5 neutron flux over a few minutes is l
l indicative of criticality or:
~A..
the point of. adding heat.
B.
supercriticality.
C.
suberiticality.
D.
equilibrium suberitical count rate.
QUESTION:
67.
i i
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 LOWER than the predicted critical rod (CEA) position if:
A.
the startup is delayed until eight hours af ter the trip.
l B.
the steam dump pressure setpoint is lowered by 100 psi prior to reactor startup.
C.
actual boron concentration is 10 ppm more than the assumed boron concentration.
D.
one control rod (CEA) remains fully inserted during the approach to criticality.
QUESTION:
68.
criticIff-0.985,howmuchreactivitymustbeaddedtomakethereactor e
With k A.
1,480 pcm (1,48% delta k/k)
B.
1,500 pcm (1.50% delta-k/k) r C.
1,520 pcm (1.52% delta k/k)
D.
1,540 pcm (1.54% delta k/k)
L FORM A Page 23 of 35
T" l
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PILESSURIEED WATER ILEACTOIL CENEft!C IVNDAMDf7A1A EKAMINATION F0ftM A i
QUESTION: 69.
1 If, during a reactor startup, the startup rate is constent and positive without any further reactivity addition, then the reactor is j
i A.
critical.
l S.
supercritical.
b C.
subt.ri tical.
D.
prompt critical.
i l
QUESTION:
70.
r Given a critical reactor operating below the point of adding heat. What
{
reactivity effects are associated with reaching the point of adding heat?
j j
A.
There are no reactivity effects since the reactor is critical, j
B.
The increase in fuel temperature will begin to create a positive l
reactiviry effect.
l C.
The decrease it fuel temperature will tegin tc create t. negativo reactf.vity effect.
l D.
The increase in fuel toaperature w!M begin to crea;0 a negative I
ranctivity of9ec.
QVESTiON:
?1.
fU Shortly after a reactor trip reactor power indicatec 7.5 percent where a stable negative $UR is at t.ained. Ru.cior power will be reduced to 0.05 percent in appecximately seconds.
~A.
360 B.
270 f
C.
180 1
D.
90 FoltM A Page 24 of 35 1
=
o PRES $URIEED WATER REACTOR CENERIC PVNDAMENTALS EXAMINATICII FORM A i
c, f
QUESTION:
72.
]
i The major reason boron is used in a reactor is to permit:
A.
a reduction in the shutdown margin.
B.
an increase in the amount of control rods (CEAs) installed, f
C.
an increase in core life.
)
D.
a reduction in the effect of resonance capture, j
i t
i r
i i
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i t
t L
f f
r l
I t
I I
FORM A Page 25 of 35 l
l
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r-PREssURIEED WATER REACTOR CDttr.1C PVNDAMNTALS BANINATION
~*
FORM A QUESTION:
73.
i An stmospheric pressure of 15 psia equals:
A.
30 psig.
B.
15 psig.
C.
5 psig, j
D.
O psig.
I l
QUESTION:
'4.
E t
Condensate depression is defined as:
A.
cooling the condensate below its saturation temperature.
{
B.
maintaining the condensate at a constant temperature throughout the system.
C.
ensuring that the condensate is below the level of the hoewell pumps, l
f D.
coolins the condensate tr. the poict of securation.
i
=
0 QUESTION:
75.
What is the reactor coolant system subcooling for lave - 400*F end pressurizar I
pressure - 1.000 psia?-
A.
75'F i
i B.
100'F C.
125'F D.
145'F FORM A Page 26 of 35
fr-e I
PRES $URIZED WATER REACTOR CENERIC WNDAMENTALS FTAMINATION FORM A
't QUESTION:
76, i
The plant is maintained at 2.000 psia with a pressurizer temperatore of 636'F.
A prersurizer safety relief valve is leaking to a collection tank which is being held at 10 psig. What is the temperature of the fluid downstream of the relief valve 7 A.
280'F B.
240'F c.
190'F D.
170'F L
f QUESTION:
77.
Overall plant efficiency will DECREASE ifl A.
the steam quality is increased by removing moisture from the steam prior to entering the turbine.
5.
ths temperature of the feedwater enterint, tha stea's generator is increased.
l l
C.
the awount of condansate depression (tiubcooling) in the main condSe.ser is l
ds;t>cred.
j D.
the traperature of the steam at. the turbine inlet is decressed.
l A
d QUESTION: 70.
i
'U The pocsibility of a water hamer is M1HD112fA by:
{
4 A.
changing valve positions as rapidly as possible, f
f B.
starting centrifugal pumps with the discharge valve fully open.
C.
starting positive displacener.t pumps with the discharge valve closed.
[
D.
venting systems prior to starting centrifugal pumps.
f FORM A Page 27 of 35 P
-,. ~.
. ~..
FRES$URIEED WATf3t REACTOR CENERIC FUNDAMENTALS EEANIMATION FORN A j
i QUESTION:
79.
j Cavitation in an operating pump may be caused by:
A.
Iowering the suction temperature.
B.
throttling the pump suction valve.
C.
throttling the pump discharge valve.
D.
increasing the pump discharge pressure, j
QUESTION:
80, i
The piping system pressure change caused by suddenly stopping fluid flow is i
f referred to as:
A.
cavitation.
[
B.
shutoff head.
0, voter haamer.
'[
D.
flew her.d.
l
' 4; f
4 QUESTION:
81, t
If a flow measurin6 134rrusent is HQI density compensated, then indicated macs ilov rate vill be:
i.
A Ch5 sava ne 2ctual mase flow rate with a chouse in temperature of the
- fluid, E,
greater than actual mass flow rate wi'.h a cecrease in temperature of the fluid.
C.
less than actual mass flow rate with a decrease in temperature of the fluid.
D.
less than actual mass flow rate with an increase in temperature of the l
fluid.
f 9
f FORM A Fage 28 of 35
i PRESSURIEF.D WATER REACTOR CENERIC WNDAMENTALS EKAMINATION l
FORM A i
QUESTION:
82.
Operating two pumps in parallel instead 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 increase in flow rate.
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.
l QUESTION:
83.
Excessive amounts of entrained gases passing through a single. phase (liquid)
I heat exchanger is UNDESIRABLE because:
A.
flow blockage can occur in the heat exchanger.
i 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 host exchanger.
QUESTION:
34.
In a two loop pressurized vater teactor, feedwater flow to each steam generator is 3.3 x 10 les/ r at an enthalpy of 419 BTU /lbs. The steam exiting h
each steam generator is at 800 psia with 100% steam quality.
Ignoring blowdown ar.d pump heat, what is the core thermal powerf 1
A.
3,411 MWt B.
2,915 MWt C.
2,212 MWt D.
1,509 MWt FORM A Page 29 of 35
~
I-I i.
L PRESSURIZED WATER REACTOR CENERIC PUNDAMDrfA13 UAN1 NATION FORN A 1
QUESTION:
85.
Why does nucleate boiling improve heat transfer in the core?
{
A.
The formation of stens bubbles at 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 J
of the coolant.
C.
Heat is removed froa the fuel rod as both sensible heat and latent heat of condensation, and the beat is transierred 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 convoction.
QUESTION:
86.
JuSsoolet nucloate boilir.g is occurring along a heated surface. Tha heat flux is then increared slightly. Vhr.t will be the effect on the delta *T betweer.
the surface and the fluid?
A.
Large it: crease in dette-T because of steam blenketing i
B.
Larr,o increase in delta T causing radia'.ive heat transfer to beconc significent C.
Small increase in delta T because of steam blanketing D.
Small increase in delta.T as varor bar.bles form and collapse i
QUESTION:
87.
What parameter change would move the plant farther away from the critical heat flux?
A.
Decrease prassurizer pressure B.
Decrease reactor coolant flow C.
Decrease reactor power D.
Increase reactor coolant temperature FORM A Page 30 of 35
e L
PRECSURIZED WATER REACTOR CDIERIC FUNDARDf7ALS EXAMINATION j
"A QUESTION:
88.
i Film boiling is:
A.
heat transfer through a vapor blanket that covers the fuel cladding.
B.
heat transfer being accomplished with no phase change.
t
?
C.
the most efficient method of boiling heat transfer.
D.
heat transfer through an oxide film on the cladding.
i 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 siong a feel rod.
C.
the core ther:nti power divided by the total reactor coolant mass flow I
rate.
4 L
D.
the number of coolant chanr.els that have reached DNB divided by the l
number of coolant channels that are subcooled.
f l
QUESTION:
90.
The reactor coolant subcooling margin will be DIRECTLY REDUCf1) by: (Evaluate each. change separately.)
l A.
increased pressurizer pressure.
B.
increased pressurizer level.
l C.
increased reactor coolant flow.
l D.
increased reacter coolant temperature.
FORM A Page 31 of 35
,o PRESSURIEF.D WATErl REACTOR CENERIC IVNDMG3tTALS EKAMINATION PORM A i
l i
QUESTION:
91.
l Maximising the elevation difference between the core thermal center and the steam generator thermal centers and minialaing flow restrictions in the reactor coolant system (RCS) piping are plant designs to:
A.
minimize the reactor coolant systea volume, j
B.
maximize the reactor coolant system flow rate during forced circulation.
C.
ensure a maximum RCS loop transit time.
l D.
ensure RCS natural circulation flow can be established.
QUESTION:
92.
i I
With the RCS subcooled 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 efter reactor trip.
C.
steam genvrator level increas..
0, stoam generator pressure decrear.o.
b QUESTION:
93.
If departure from nucleate boiling (DhB) is reached in the coro, the surface resperature of the fuel clad will:
A.
increase rapidly.
B.
decrease rapidly.
i t
C.
increase gradually, D.
decrease gradually.
i t
i
{
\\
l I
1 l
FORM A Page 32 of 35 i
PRESSURIEED WATER REACTOR CDfERIC FUNDMtDffA1A EKAMINATICII o
yngg 4 QUESTION:
94.
If the reactor is operated within core thermal limits, then:
A.
plant thermal efficiency is optimited.
I B.
fuel cladding integrity is ensured.
l C.
Pressurized thermal shock will be prevented.
D.
Reactor vessel thernal stresses will be minimited.
t QUESTION:
95.
Fast neutron irradiation of the reactor vessel results in stresses j
within the vessel metal, thereby the Nil Ductility Transition Temperature.
l A.
increased, increasing B.
increased, decreasing C.
docreased, increasing D.
decreased, decreasing QUESTION:
96.
The like.lihood of brittle fracture failure of the reactor vascel is LTOUCED by:
A.
increasing vessel age.
[
B.
reducing vessel pressure.
C.
reducing vessel temperature.
l D.
reducing gamma flux exposure.
1' l
r I
l l
l 1
FORM A Page 33 of 35
FT
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PRESSURIZED WATM REACitNL CENm1C PWDANMTALS RAMINATION l
PORM A QUESTION:
97.
Pressure stress on the reactor vessel vall is:
f 1
A.
compressive across the entire wall.
]
i B,
tensile across the entire vall.
i C.
tensile at the inner wall, compressive at the outer wall.
D.
compressive at the inner all, tensile at the outer vall.
i QUESTION:
98.
The nil. duett 11ty temperature is that temperature:
A.
below which the probability of brittle fracture significantly increases.
b.
wh6te fai*.ure stress becomes greater than the yield. stress of the metal.
C.
below which the probability of plostic deformation sir,nificantly increases.
D.
below which the yield stress of the metal is higher than the crittcal j
frs:ture strest.
t QUESTION:
99.
j Pressurized thermal shock could most likely be a concern during.
j A.
an uncontrolled cooldown followed by a rapid repressurization.
B.
an uncontrolled depressurization followed by a rapid repressurization.
l l
C.
an uncontrolled cooldown followed by a rapid depressurization.
1 1
l D.
an overpressurization from a low temperature low. pressure condition.
l l
t FORM A Page 34 of 35
a--
O PILESSURIEED WATER REACTOIL CENERIC ITNDANENTALS EKANINATION FORM A t
QUESTION:
100.
During a severe overcooling transient, a major concern to the operator is:
A.
accelerated tirconium 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.
i t
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i i
L FORN A Page 35 of 35 l
i-UNITED $TATES NUC1. EAR RECUIATORY COMMI$$ ION
[
PRESSURIZED WATER REACTOR CENERIC TUNDAMDrfAI.S EXAMINATION j
I i
i Please Print:
Name:
j Tacility:
f ID Number:
i INSTRUCTIONS TO CANDIDATE Use the answer sheet provided.
Each question has equal point value.
The passinE Erader regtnire at least 80% on this part of the written licensing examination, fill 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, i
SECTION Questicas 4 of Total Score THERMODYNANICS 1 - 26
~
00hrONENTS 29 71 REACTOR TdEORY 72 100 l
TOTALS 100 l
All work done on this examination is my own.
I have neither given nor received aid, t
Candidate's Signature i
l l
NB
+
-~-. _.
l e
RULES AND GUIDELINES FOR THE CENERIC FUNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:
i (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.
[
(4) Three handouts are provided for your us, during the examination, an l
Equations and Conversions sheet, instructions for filling out the answer sheet, and Steam Table booklets, t
L (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 shvet.
(6) Scrap paper will be provided for calculations.
(7) Any questions about an iten on the examination should be directed to the examiner only.
l (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 tise.
In order to avoid the appearance or poscibility 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.
l (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.
I l
l
OMERIC FIREWEETAIA EKAIONATICII SECTICII EQUATICIts AND 00ItVERS101tS MANDOUT SMEET l
i EIQ&f1Mt3 I
Cycle Efficiency Nat Mark (out) i
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j 6
5 Ah SCR
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UA AT CRg (1. K,gg)1 -32(
eff)2 SUR - 26,06/r N
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CR /CR F
g 0
l 26.06 (A,gg p)
(1. X,gg)0 (E
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(1. X,gg)g l
4 P, 10 " I")
P (1. K,gg)/K,gg SDN P,a(*/')
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i p
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t i
CONVERSIMS 10 1 Curie 3.7 x 10 dps 1kl 2.21 lba 3
0 1 hp 3.41 x 10 STU/hr 2.54 x 10 3TU/hr 1 Mw i
1 STU 778 ft lbf
'F 9/5 'C + 32
'C 5/9 (*F. 32)
P t
l l
l l
l 1
Io PRESSURIZED WATER REACTOR CENERIC FUNDAMDtTALS RIANIMATION o
FORN &
l
-QUESTION:
1.
An atmospheric pressure of 15 psia equals:
A.
30 psig.
)
8.
15 psig.
i C.
5 psig.-
l D.
O psig.
)
QUESTION:
2.
Condensate depression is defined as:
l t
A.
cooling the condensate below its saturation temperature.
1 B.
maintaining the condensate at a constant temperature throughout the system.
C.
onsuring thtt the condensate is below the level of the hotwell pumps.
D, cooling the condensate to the point of sate. ration.
i i
QUESTION:
3.
What is the reactor coolant system subcooling for Tave - 400'F and pressurizer pressure - 1,000 psia?
A.
75'T I
B.
100'r C.
125'F l
I D.
145'F l
i' l
I l
l l
l l
l-PORN B Page 1 of 34 l
1
c.
FRESSURIZED WATER REACM CENERIC FUNDAMENTA1A EIANIMATION FORM B
-QUESTION:
4.
The plant is maintained at 2,000 psia with a pressurizer temperature of 636'F.
A pressurizer safety relief valve is leaking to a collection tank which is being held at 10 psig. What is the tesperature of the fluid downstream of the i
relief valve?
l I
A.
280'r B.
240'r f
C.
190'F D.
170'F i
i QUESTION:
5.
j Overall plant efficiency will DECKEASE if:
A.
the steam quality is increased by removing moisture from the steam prior j
to entering the turbine.
B.
the temperature of the feedvater entering the steam generator is incrassed.
t C.
the amount of condensate depreasion (subcooling) in the main condenser is decreased.
D.
the temperature of the steam at the turbine inlet is decreased.
l QUESTION:
6.
The possibility of a water hammer is NINIKIEED by:
l l
A.
changing valve positions as rapidly as possible, i
B.
starting centrifugal pumps with the discharge valve fully open.
(
C.
starting positive displacement pumps with the discharge valve closed.
[
l D.
venting systems prior to starting centrifugal pumps.
l l
FORM B Page 2 of 34
~
FRESSURIEED WATER REACTOR CDIERIC MfitDAltDf7A1.8 EKAMINATION FORM 5 l
QUESTION:
7.
Cavitation in an operating pump may be caused by:
A.
Iowering the suction temperature.
l l
t 8.
throttling the pump ruction valve, j
i C,
throttling the pump discharge valve.
D.
increasing the pump discharge pressure.
)
I i
QUESTION:
8.
l i'
The piping system pressure change caused by suddenly stopping fluid flow is referred to as.
1 A.
cavitation.
l 2.
shutoff head.
1 C.
water hcamer.
D.
flow head.
QUESTION:
9.
t If a flow measuring instrument is ggI density compensated, then indicated mass flow rate will be:
i i
A.
the same as actual mass flow rate with a change in temperature of the l
fluid.
i B.
greater than actual mass flow rate with a decrease in temperature of the fluid.
t C.
less than actual mass flow rate with a decrease in temperature of the j
fluif.
l D.
less than actual mass flow rate with an increase in temperature of the f
fluid.
1 l
l FORM B Page 3 of 34 f
.e, n
---,-,.-,-.,---.----n-
--. - -. - - --J
o FRESSURIEED nlATR REACTTIR CENDt!C WNDAMDffA10 ftANINATION FORN &
QUESTION:
10.
l Operating two pumps in parallel instead of operating a single pump will result in:
l A.
a large increase in system head and the same flow rate.
[
t B.
the same system head ai.
= small increase in flow rate.
C.
a small increase in systen heat and a large increase in flow rate.
D.
a decrease in systen head and a large increase in flow rate.
i QUESTION:
11.
l Excessive amounts of entrained gases pbssin5 through a single. phase (liquid)
[
heat exchanger is IEfDfBIRA112 becaoset A.
flow blockage can occur in the heat 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.
I l
In a two. loop pressurized water reactor, feedwater flow to each steam l
I generator is 3.3 x 10 lba/hr at an enthalpy of 419 BTU /lbs. The steam exiting each steam generator is at 800 psia with 100% stean quality. Ignoring blowdown and pump heat, what f.s the core thermal power?
A.
3,411 We i
B.
2,915 We l
C.
2,212 Wt l
D.
1,509 We i
l l
1 FORM B Page 4 of 34 e
O MLESSURIEED WATI3t REACTOR CDfERIC MINDANENTA1.S KRANIMATION a
PotN B QUESTION:
13.
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.
i B.
Heat is removed from the fuel rod as both sensible heat and latent heat of vaporization, and the motion of the steam k"bbins cause rapid mixing of the coolant.
C.
Heat is removed from the fuel rod as both sensible heat and latent heat I
of condensation, and the heat is transferred directly to the coolant by
[
I tadiativa heat transfer.
i 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 transfotred by convection.
QUESTION:
14.
Subcooled nucleate boiling is occurring along a heated surface.
The heat flux i
is then increased slightly. Whct 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
QUESTION:
15.
What parameter change would move the plant farther away rros the critical heat flux?
A.
Decrease pressurizer pressure B.
Decrease reactor coolant flow C.
Decrease reactor power D.
Increase reactor coolant temperature FORN B Page $ of 34
u PRESSURIEED nlATR REACTOR CDfERIC PMMOf7ALS h:KANIMATION i
i FORM S QUESTION:
16.
Tilm boiling is:
l t
i A.
heat transfer through a vapor blanket that covers the fuel cladding, i
[
B.
heat transfer being accomplished with no phase change, C.
the most efficient method of boiling heat transfer, f
D.
heat transfer through an oxide filn on the cladding.
QUEST 10Ni 17.
i The departure from nucleate boiling retto I.DNLR) is defined as:
{
A.
the actual heat flux divided by the critical heat. flux at any point along l
a fuel rod.
B.
the critical heat f1 4 divided by the actual heat flux at any point along a fuel rov..
C.
the core thermal power divided by the total reactor coolant mass flow rate.
j D.
the number of coolant channels that have reached DNB divided by the j
number of coolant channels that are subcooled.
J QUESTION: 18.
i The reactor coolant subcooling margin will be p1HCTLY REDUCED by: (Evaluate
[
each change separately.)
j A.
increased pressurizer pressure.
B.
increased pressurizer level.
C.
increased reactor coolant flow.
i D.
increased reactor coolant temperature, t
i FORM B Page 6 of 34 l
l
e o
i PRF.SSUR1EED WATER REACTOR CElNDLIC WNDAMENTALS EKAMINATION o
PORM B i
QUESTION: 19.
Maximiting the elevation difference between the core thetaal center and the steam generator ihermal centers and minimizing flow restrictions in the reactor coolant system (RCS) piping are plant designs to:
l A.
ainimize the reactor coolant system volume, t
B.
maximize the reactor coolant system flow rate during forced circulation.
1 h
C.
ensure a maximus RCS loop transit time, D.
ensure RCS natural circulation flow can b6 established.
I QUESTION:
20.
With the RCS subcooled and all RCPs stopped, the natural circulation flow rate l
will 302 b& affected by an increase in the:
A.
reactor coolant pressure increase.
4 B.
time af ter reactor trip.
C.
steam generator level increase.
}
D.
steam generator pressure decrease.
QUESTION: 21.
If departure from nucleate boiling (DNB) is reached in the core, the surface l
temperature of the fuel clad will:
l A.
increase rapidly.
B.
decrease rapidly.
C.
increase gradually.
D.
decrease gradually, l
k FORM B Page 7 of 34
FILESSURIZED WATut RfACTOR CIlNDt1C FUNDMtENTALS EKAMINATION l
FORM B
(
i i
QUESTION:
22.
If the reactor is operated within core thermal limits, then:
l 1
A.
plant thermal efficiency is optimized.
\\
B.
fuel cladding integrity is ensured.
C.
pressurized thermal shock will be prevented.
D.
reactor vessel therJe1 stresses will be miniaired.
}
l i
QUESTION:
23.
rast neutron irradiation of the reactor vessel results in stresses i'
within the vessel vett.1, thereby the Nil. Ductility Transition Temperature.
A.
increased, inc" easing j
B.
tneressed, decreasing i
C.
decreased, increasing D.
decreased, decrea ing i
QUESTION:
24.
f The likelihood of brittle fracture failure of the reactor vessel is REDUCED by:
A.
increasing vessel age.
f 8.
reducing vessel pressure, i
C.
reducing vessel temperature.
D.
reducing gamma flux exposure.
l i
f I
FORM B Page 8 of 34
t rRESSUR1EED WATER REACTOR CENERIC FUNDAMDfTA1A EXAMINATICII j
roRn s QUESTION:
25.
Pressure stress on the reactor vessel wall is:
l t
A.
compressive across the entire wall.
]
i j
5.
tensile across the entire wall.
f C.
tensile at the inner well, compressive at the outer wall, I
D.
compressive at the lun6r all, tensile at the outer waM.
.I QUECION: 26.
i The nil ductility temperature is that temperature:
A.
below which thi probability of brittle fracture significantly increases.
B.
shere failure stress becomes greater than the yield stress of the metal, f
I C.
below which the probability of plastic deforsation significantly
[
increases, i
D.
below which the yield stress of the metal is higher than the critical t
i fracture stress, t
QUESTION:
27.
i 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.
l C.
an uncontrolled cooldown followed by a rapid depressurization, f
D.
an overpressurization from a low temperature, low pressure condition.
QUESTION:
28.
During a severe overcooling transient, a major concern to the operator is:
i I
A.
accelerated zirconium hydriding.
i B.
loss of reactor vessel water level.
C.
loss of reactor coolant pump not positive suction head.
D.
brittle fracture of the reactor vessel.
FORM B Page 9 of 34
.. _, ~
c l.
FRFSSURIEED WATm REACTOR CENERIC FUNt*KENTA13 EIANIMATICIt FoltM B QUESTION:
29.
t The primary purpose of a pressure relief valve is to:
A.
maintain system flow.
B.
aaintain systen pressure.
C.
maintain systou integrity.
D.
heinthin system temp 0reture.
QUESTION:
30.
t When a discharge valve ir opened to atmosphere, the pressure on the upstrean j
side of the valve will:
t A.
remain the sans, and the pressure on the downstreau eide will increase.
l i
B.
increase, and the pressure on the downstrean side will remain the saac.
i C.
remain the same, and the pressure on the downstrema side will decrease.
D.
decrease, and the pressure on the downstream side will remain the same.
l QUESTION:
31.
j The function of a valve backseat is to:
t A.
isolate system pressure from the packing and stuffing box to minimize i
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, f
D.
provide a backup means of flow isolation in the event of a pipe break.
1 4
FORM B Page 10 of 34 f
PItESSURIZED WATER REACT 00L CENERIC FUNDAMENTA1J EKAMINATICN 700tM B QUESTION:
32.
After manually positioning a motor. operated valve, how is the valve actuator re. engaged?
)
A.
Actuation of the torque switch B.
Monually pulling up on the manual declutch lever C.
Actuntion of either the full.open or full closed limit switch l
t
?
D.
Actuation of the valve actuator motor in eitbtr the open or close dirtetier.
QCESTIN:
33.
to verify the positisn of a closed wanual valve, the operster should operate the valve:
A.
to the fully open p(.sition, 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 manual force.
D.
in the closed direction until it stops, then close it an additional one half turn using normal force.
i QUESTION:
34 Density compensation is used in flow instruments to change to A.
mass flow rate, volumetric flow rate B.
volumetric flow rate, mass flow rate l
C.
fluid pressure, volumetric flow rate D.
differential pressure, mass flow rate l
4 l
l FORM B Page 11 of 34 l
l e.
PRESSURIEED WATER REACTOR CENERIC PVNDAMENTAIJ EKAXINATION i
roRM a i
i
' QUESTION:
35.
I If the liquid flowing throuSh a liquid flow rate sensor contains entrained voids (gas or steam), indicated flow rate will be:
l A.
erroneously high.
l E.
erroneously low.
C.
unaffected.
i I
fluctuating.
to-QUESTION:
30.
If the equalicing line on a differential pressure CD/P) f1mi detector is opened, the f1w detector indication will:
[
A, increase slightly.
B.
decrease slightly.
C.
go to zero.
D.
not change.
i I
l QUESTION:
37.
l Flow detectors (such as an orifice, flow nozzle, and ventu:1 tube) measure flow rate using the principle that flow rate is:
A.
DIRFCTLY proportional to the differential pressure.
L B.
INVERSELY proportional to the differential pressure.
C.
DIILECTLY proportional to the square root of the differential pressure, l
?
t i
D.
INVERSELY proportional to the square root of the differential pressure.
l I
I t
t FORM B Page 12 of 34 G.
(_ - _
e 1
FRESSURIEED WATIlR REACTOR GENERIC FUNDAMENTA12 EKANINAT10N FORN B QUESTION:
38.
The pressure differential between a reference leg and a variable leg is:
A.
DikECTLY proportional to the height of the variable leg.
I B.
INVEksELY proportional to the height of tl.e variable leg.
i C.
ElREGILY proportionni to the der.sity of the reference leg.
D.
IMfER$LLY proportional to the tempe.rature of the referfince le6-t i
QUESTION:
35, it the reference leg of a differential ptes9ure IcVel indicator experiences high ambient temperature, indic.ated 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:
40.
The output fer a reference leg differential pressure level instrument will fail 13 as a result of A.
a break on the reference leg.
B.
a rupture of the diaphraga in the differential pressure cell.
C.
the reference leg flashing to steam.
D.
a break on the variable leg.
t i
i t
FORM B Page 13 of 34 n.
...a
,,, -. -,. ~, -
PRESSURIZED WATER REACTOR CENERIC FUNDAMENTAIA EKAMINATION j
PORM B QUESTION:
41.
A resistance temperature detector (RTD) operates on the principle that the change in electrical resistance of:
A.-
two dissimilar metals is PIRECTLY proportional to the ti,mperature change measured at their junction.
B.
two dissimilar metals is INVERSELY proportional to the temperature change measured at their junction.
C.
a metal is DIRECTLY proportional to its change in temperature.
D.
a metal is INVERSELY proportional to its change 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 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 QUESTION:
43.
I Scintillation detectors eperate on the principle of:
I
\\
A.
photodisintegration.
u 1
B.
photokinesis.
l l
C.
photomultiplication.
D.
photoionization.
1 1.
l l
l FORM B Page 14 of 34 l.
I PRESSURIZED WATER REACTOR CDIERIC FUNDAMENTA1J EXAMINATION FORM B
,e-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 l
signal and yields a neutron only signal for indication use.
C.
Gamma induced detector pulses are of insufficient width to generate a significant log level amplifier output. Neutron pulses are the only ones with sufficient width to yield a neutron enly 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 pulr-a vielding a neutron only signal for indication use.
QUESTION:
45.
The difference between the setpoint and the measured parameter in an automatic flow controller is called:
A.
gain.
B.
bias.
l C.
feedback.
D.
error.
l 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.
FORM B Page 15 of 34
,m
r PRESSURIZED WATER REACTOR GENERIC FUNDAMENTA1J EXAMINATION FORM B l
r 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.
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:
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 automatic mode and manual mode.
B.
Ensure that the valve controller output signals are matched between automatic 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:
49.
l An indication of centrifugal pump cavitation is:
A.
pump motor amps pegged high.
B.
pump discharge pressure indicating zero.
l C.
pump motor amps oscil1.ating.
D.
pump discharge pressure indicating shutoff head.
l l
l FORM B Page 16 of 34
PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION i
FORM B j
QUESTION:
50.
i The term " shutoff head" for a centrifugal pump indicates that it is pumping st:
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 extended periods of time with no flow through the pump will cause:
i A.
pump failure from overspeed.
B.
pump failure from overheating.
C.
motor failure from overspeed.
D.
motor failure from overheating.
QUESTION:
52.
SHUTTING the discharge valve on an operating centrifugal pump will cause the HQIQB AMPS to and the pump DISCHARCE PRESSURE to I
A.
increase, increase B.
decrease, increase I
C.
increase,' decrease D.
decrease, decrease I
FORM B Page 17 of 34
g- -
FRESSURIZED WATER REACTOR GDIERIC FUNDAMENTALS EKANINATION y0RM B QUESTION:
53.
If the speed of a positive displacement pump is increased, the available' net positive suction head (NPSH) will and the probability of
- V, cavitt. tion will i
g A.
increase, increase B.
decrease, decrease l
C.
increase, decrease D.
decrease.. increase QUESTION:
54.
Reactor coolant pump motor amps will if the rotor is LQGEED and j
1
-the motor speed will if the rotor EHE&B3, A.
increase, increase B.
increase, decrease 4
l C.
decrease, increase 1
D.
decrease, decrease 1
QUESTION:
55.
i l~
If the generator bearings on a motor generator overheat then:
A.
'the generator voltage will increase.
1 B.
the generator windings will overheat.
C.
the motor current will decrease.
1 l
D.
the motor windings will overheat.
FORM B Page 18 of 34
r I
FRESSURIZED WATER REACitNt CENERIC FUNDAMFXTALS T.AAMINATION PORM B QUESTION:
56.
If the speed of a variable speed centrifugal pump is increased to cause pump flow rate.to double, pump motor current will:
t
- A.
remain constant.
L.,
increase two. fold (double).
C.
increase four fold.
D.
increase eight fold.
QUESTION:
57.
The-starting current in an A.C. motor is significantly hi her than the 5
L full load running current because:
1 l
A.
starting torque is lower than running torque.
B.
starting torque is higher than running torque.
{
is C.
rotor current during start is higher than running current.
D..
rotor current during start is lower than running current.
1
(
QUESTION:
58.
The number of starts for an electric motor in a given period of time should be limited because:
p 1-A.
overheating of the windings can occur.
1 B.
excessive torque is generated during motor start.
l L
L C.
running current is much higher than starting current.
D.
motors are normally started under full load conditions.
l L:
I FORM B Page 19 of 34
PRESSURIZED WATER REAC10R CENERIC FUNDAMENTALS EKANINATION j
FORM B QUESTION:
59.
severe stress in e mechanical component, induced by a sudden, unequally I
distributed temperature reduction is a description of:
A.
heat stress.
B '.
thermal shock.
l C.
thermal strain.
D.
heat strain.
?
QUESTION:
60.
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 throu5h 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 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.
C.
Dilution of the borated water system.
D.
Shell pressure will decrease.
FORM B Page 20 of 34
PRESSURIZED WATER REACTOR CENERIC WNDAMENTALS EKANINATION FORM B QUESTION:
62.
i What is the reason for bypassing a desineralizer due to high temperature?
A.
Resins expand and restrict flow through the demineralizer.
B.
The demineralizer decontamination factor is dramatically increased.
C.
Organic compounds used as resins will decompose.
D.
The creatior, of preferential flowpath through the demineralizer will occur.
QUESTION:
63.
In the event of a system crud burst, what adverse effect does the crud burst have on demineralizer operation?
A.
Increases pressure drop across domineralizer B.
Increases flow rate through demineralizer C.
Increases demineralizer outlet conductivity D.
Increases demineralizer inlet pH I
QUESTION:
64.
Boron concentration in the reactor (primary) coolant system has been de-creasin5 steadily at approximately 10 ppe per hour while using the deborating I
l demineralizer. After several hours, the rate decreases to 2 ppe per hour.
l What is a possible cause for the change in deboration rate?
l l
l A.
Temperature of the coolant passing through the domineralizer has decreased.
l B.
pH of the coolant has increased significantly.
C.
Flow through the deborating resins has increased sharply.
D.
Deboratin6 resins have become boron saturated.
FORM B Page 21 of 34
I PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXANINATION f
PORM B QUESTION:
65.
i To de energite a component and its associated control and indication circuits, the component circuit breaker should be:
A'.
racked in and tagged in open position.
l B.
racked in and tagged in closed position, j
C.
racked out and tagged in racked out position.
e D.
in the test position and tagged in test.
I QUESTION:
66.
i To ensure reliable local breaker indication is being provided the must be reset after breaker operation.
l l
A.
OPEN/ CLOSED mechanical flag B.
OPEN/ CLOSED indicating lights T
C.
Overcurrent trip flag
^
D.
Spring CHARCE/ DISCHARGE flag k
. QUESTION:
67.
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.
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 the primary current.
FORM B Paga 22 of 34
o 1
PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALE EXANINATION FORM B j
QUESTION:
68.
Loss of circuit breaker control power will cause:
q l
!+
A, breaker line voltage to be zero regardless of actual breaker position.
B.
the remote breaker position to indicate closed regardless of actual breaker position.
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 closing the output breaker of a three phase generator onto the bus, then:
A.
sn overvoltage condition will occur on the bus.
B.
an overcurrent condition will occur on the generator.
C.
an overvolta6e condition will occur between generator phases.
D.
generator undervoltage relay actuation will occur.
QUESTION:
70.
Which of the following statements is correct concerning the use of disconnect switches?
l A.
Disconnects should be limited to normal load current interruption.
L B.
Disconnects may be used to isolate transformers in an unloaded network.
C.
Disconnects are similar to oil circuit breakers, but are manually l
operated.
l l
D.
Disconnects must be closed with caution when under load because of l
possible arcing.
1 l
1 l
l' 1
l l
l' l
FORM B PaBe 23 of 34 l
l
.s-
' Y PRF.SSURIZED WATER REACTOR CENERIC FUNDAMENTALS EKAMINATION FORM B
'.\\
QUESTION:
71.
Closing a' generator output breaker with the generator frequency much less than grid frequency will cause the generator to trip on:
A.
reverse power.
B.
overvoltage.
C.
D.
QUESTION:
72.
The operator has just pulled control rods and changed the effective multipli-cation factor-(Keff) from 0.998 to 1.002. The reactor is:
i A.
prompt critical B.
supercritical C.
exactly critical D.
suberitical 1
l i
l l
l l
l i
l PDRM B Page 24 of 34
.. -. _ _. - ~, - -
l'.
.I J*
PRESSURIZED WATER REACTOR CENERIC PUNDAMENTALS EKAMINATION l
y PORM B i
QUESTION:
73.
The ratio of the number of neutrons in one generation to the number of i
r.autrons in the previeus generation is the:
A.
effective multiplication factor B.
fast fission factor i
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 FORM B Page 25 of 34
t PRESSURIZED UATER REACTOR CENERIC FUNDAMENTALS EKANINATION l
O
=
h FORM B e
QUESTION:
76.
Over core life the' production of plutonium isotopes with delayed neutron a
fractions than uranium delayed neutron fractions will cause reactor. power transients to be near the end of core life.
A.
less, faster B.
less, slower C.
greater, faster
't D.
greater, slower QUESTION:
77.
An installed neutron source:
A.
maintains.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 subcritical reactor.
C.
generates a sufficient neutron population to start the fission process and initiate suberitical multiplication.
D.
provides a neutron level that is detectable on the source range nuclear instrumentation.
f QUESTION:
78.
Why does increasing reactor coolant boron concentration cause the moderator temperature coefficient to become less negativc?
A.
Reactor coolant temperature increases result in a larger increase in the 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.
D.
The change in tesonance escape probability dominates the change in the thermal utilization factor.
FORM B Page 26 of 34
~
t FRESSURIZED WATER REACTOR CENERIC FUNDAMENTA13 EXAMINATION FORM B QUESTION:
79.
' Why does the fuel temperature (Doppler) coefficient becomes less negative at higher fuel temperatures?
A.
As reactor power increasen, the rate of increase in the fuel temperature diminishes.
B.
Neutrons penetrate deeper into the fuel, resulting in an increase in the fast fission factor.
C.
The amount of self-shielding increases, resulting in less neutron absorption by the inner fuel.
D.
The amount of Doppler broadening per degree change in fuel temperature diminishes.
QUESTION:
80.
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 B.
a rate of, differential C.
a differential, total D.
a total, differential 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.
t.
FORM P Page 27 of 34 e
~-
[
PRESSURIZED WATER REACTOR GENERIC FWDAMENTALS EKAMINATION 1
FDRM B QUESTION:
82.
As moderator temperature increases, the magnitude of differentiel rod (CEA) worth increases because:
A.
decreased moderator density causes more neutron leakage out of the core.
B.
moderator temperature coefficient decreases, causing decreased competition.
C.
fuel temperature increases, decreasing neutron absorption in fuel.
D.
decreased moderator density increases neutron migration length, a
QUESTION:
83.
Control rod (CEA) bank overlap:
A.
provides a more uniform differential rod (CEA) worth and axial flux distribution.
B.
provides a more uniform differential rod (CEA) worth and allows 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 ensures rod (CEA) insertion limits are not exceeded.
i l
D.
ensures that all rods (CEAs) remain within their allowable tolerance between individual position indicators and their group counters and provides a more uniform axial flux distribution.
L I
QUESTION:
84.
The basis 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 B Page 28 of 34 l
PRESSURIZED WATER REACTOR CENERIC WNDAMENTALS EXAMINATION FORM B QUESTION:
85.
l The control rod insertion limits are power level dependent because the magnitude of:
1 A.
control rod worth decreases as power increases.
B.
power defect increases as power increases.
C.
Doppler (fuel temperature) coefficient decreases as power increases.
D.
moderator temperature coefficient increases as power increases, QUESTION:
86.
Fission products that have substantial neutron capture cross sections are:
A.
excited fission products.
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:
i 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.
FORM B Page 29 of 34
f P'
~ ~
PRESSURIZFD WATER REACTOR CENERIC PUNDAMENTAIJ EXAMINATION
.e-yggy 3 QUESTION:
88.
Following a reactor trip from sustained high power operation, the major Xenon
!~-
135 removal procesa is:
A.
ion exchange.
[.
B.
beta decay.
C.
neutron' capture.
D.
alpha decay.
QUESTION:
89.
A reactor has been operating at 50 percent power for 7 days when power is ramped to 100 percent over a four hour period. The new equilibrium Xenon value will:
A.
be twice the 50 percent value.
i B.
be less than twice the 50 percent value.
C.
be more than twice the 50 percent value.
D.
remain the same since it is independent of power, i
?
QUESTION:
90.
1 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.
1 i
B.
Xenon override.
I L
C.
Xenon burnup.
i l
l D.
Xenon oscillation.
i i
l i
FORM B Page 30 of 34
~ '
PRESSURIEED WATER REACTOR CENERIC PUNDAMENTAIA EXAMINATION PORN 5 i
QUESTION:
91.
]
A reactor that has been operating at rated power for about two weeks reduces i
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 /> l
B.
20 to 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> J
C.
30 to 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> v
D.
40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> i
QUESTION:
92.
The reactor is near the end of its operating cycle.
In order to stay g
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 difforential 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:
93.
While withdrawing control rods during an approach to criticality, the count L
[
rate doubles. What will occur if the same amount of reactivity that caused the first doubling is added again?
A.
Count rate will increase slightly.
l B.
Count rate will double.
L C.
The reactor will remain suberitical.
1 D.
The reactor will be critical or slightly supercritical, p
l.
l l
e FORN B Page 31 of 34 y
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,m, y-.,,, _.,,-.,., -.
PRESSURIZED WATER REAC1VR GENERIC FUNDAMENTALS ERAMINATION FORM B QUESTION:' 94.
i In a reactor with a source, a non changing neutron flux over a few minutos is indicative of criticality or:
r t
A.-
'the point of adding heat, B.
supercriticality.
l C.
.suberiticality.
D.
equilibrium subcritical count rate.
QUESTION:
95, t
At EOL, critical rod (CEA) position has been calculated for a reactor startup i
four hours after a trip from 100 percent power equilibrium conditions. The actual critical rod (CEA) position will be LOWER than the predicted critical j
i 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 reactor startup.
C.
actual boron concentration is 10 ppm more than the assumed boron concentration, i
D.
' one control rod (CEA) remains fully inserted during the approach to criticality.
I l'
l QUESTION:
96.
1 With keff - 0.985, how much reactivity must be added to make the reactor critical?
l A.
1,480 pcm (1.48% delta k/k) l L
B.
1,500 pcm (1.50% delta k/k) 1 C.
1,520 pcm (1.52% delta k/k) 1 D.
1,540 pem (1.54% delta k/k) 1 1
l j
1 FORM B Page 32 of 34
J PRESSURIZr.D MATER REACTOR CENERIC MINDAMENTALS EXANINATION
^
,og,g i
QUESTION:
97.
If, during a reactor startup, the startup rate is constant and positive
'J without any further reactivity addition, then the reactor is:
A.
critical.
B.
supercritical.
C.
suberitical.
^
D.
prompt critical.
t QUESTION:
98.
Civen a criticel reactor operating below the point of adding heat, what reactivity effects are associated with reaching the point of adding hekt?
A.
There are no recctivity effects since the reactor is critical.
B.
The increase in fuel temperature will begin to create a positive P
reactivity effect.
C.
The decrease in fuel temperature will begin to create a negative i
reactivity effect, D
The increase in fuel temperature will begin to create a negative reactivity effect.
r QUESTION: 99.
Shortly after a reactor trip, reactor power indicates 0.5 percent where a stable negative SUR is attained. Reactor power will be reduced to 0.05 percent in approximately seconds.
A 360 B.
270 C.
180 l-D.
90 L
l-1 FORM B Page 33 of 34 1
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t
, o;c e o g-PRESSURIZED WATER REAC10R CENERIC WNDAMENTALS EKANINATION l
NI
[.
L QUESTION:
100.
' The major. reason boron is used in a reactor is to permit:
A.
a reduction in the shutdown margin.
B.
an incrdase in the amount of control rods (CEAs) installed.
C.
an increase in core life.
D.
a reduction in the effect of resonance capture.
o t
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i i
i
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1 i
i I
FORM B Page 34 of 34 i
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A