ML19324B773
| ML19324B773 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/26/1989 |
| From: | Gallo R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Thompson W GENERAL PUBLIC UTILITIES CORP. |
| References | |
| NUDOCS 8911080195 | |
| Download: ML19324B773 (79) | |
Text
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- 'g NUCLEAR REGULATORY COMMISSON j
y
- g REQloN I 475 ALLENDALE RoAb p.
KING OF PRUSSIA. PENNSYLVANIA 1HM g
Docket No. 50-289 GPU Nuclear Corporation ATTN:
Mr. W. Thompson l
Operator Training Manager P. O. Box 480
..t Middletown, Pennsylvania 17057
Dear Mr. Thompson:
On October 4,
1989, the SF,C administered the Generic Fundamentals Examination Section (GFES) of the written.cperatot licensing examination to employecs of your facility.
Enclosed with this letter are copiea 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 s
grade for this examination; passing grade for the GFES is 80%.
In accordance with 10 CFR 2.790 of the Commission'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 indivicW1 examinees are
?
. exempt from disc]osure, therefore enclosures (3) anc (4) will not be l
e placed in the PDR.
should you have any questions concerning this examination, please contact Mr. Paul Doyle at (301) 492-1047.
Sincerely, i
it g
r Robert M. Gallo, Chief Operations Branch Division of Reactor Safety 1
Enclosures:
I 1.
Examination Form "A" with answers 2.
Examination Form "B" with answers l
3.
Examination Results Summary for facility
[
4.
Copies of Candidates individual answer sheete l
l L
l GFFICIAL RECORD COPY p.
1' ADOCK 05000289(t L
8911000195 891026 2
O,U PDH V
P?iU ]
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t cc w/o enclosures i
T. G. Broughton, Operations and Maintenance Director, TMI-1 C. W. Smyth, Manager, TMI-1 Licensing R. J. McGoey, Manager, PWK Licensing Ernest L. Blake, Jr., Esquire TMI-Alert (TMIA)
Susquehanna Valley Alliance (SVA)
Public Document Room (enclosures 1 and.2 only) i NRC Resident Inspec* r l,
Commonwealth of_Pennsyl.
.._3 bec w/o enclosures:
d7 Region I Docket Room (withconcurrences)
Management Assistant, DRMA.
.P. Doyle, OLB-OL Facility File s
4 OFFICIAL RECORD COPY
$NS$
10/ /89 10/td/89 10 9
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l ANSWER KEY PWR GFE (FORM A) i 1.
C.
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.
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.
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91.
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42.
B.
67.
B.
92.
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18.
C.
43.
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68.
C.
93.
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19.
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44.
B.
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B.
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B.
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A.
71.
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96.
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22.
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23.
B.
48.
A.
73.
D.
98.
A.
24.
B.
49.
D.
74.
A.
99.
A.
25.
D.
50.
A.
75.
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100. D.
Pressurized Hator Reactor,eneric Fundamentals Examination r
administered October 4,1989.
Questions 14, 39 and 56 were deleted.
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, e, i UNITED STATES NUCLEAR REGUIATORY COMMISSION PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION Please Print:
Name:
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 COMPONENTS 1
43 REACTOR THEORY 44 72 l
THERMODYNAMICS 73 100 j'
TOTALS 100 l
l All work done on this examination is my own.
I have neither given nor received aid.
o l
l Candidate's Signature l
l l
l PDRM A
c
}
, ' f, RULES AND GUIDELINES FOR THE GENERIC FUNDAMENTALS EXA!!INATION i'M' 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 '.n the nrme of the facility you are associated with.
(3)
Fill in the ID Number you were given at-registratior.
1 (4) Three hando w s are provided for your use during the examination, an l
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 i
answers marked on this sheet.
Follow the instructions for filling out the answer sheet.
(6) Scrap paper will be provided for calculatiow.
(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 auton.atic forfeiture of this examination. Cheating could also result in suvere penalties.
l (9) Restroom trips are limited. Only 0FE examinee may leave the room at a l
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, pir.se sign the statement ou the cover sheet indicating that the work is your own and you have not received or been given any assistance in completing the examination.
l (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 af ter leaving you are found in the i
examination area while the examination is in progress, your examination may be forfeited.
i
- 3
. e CENERIC FUNDANETAIJ EIANIMATION SECTION EQUATIONS AND CONVERSIONS HANDOUT SHEET C
EDUATIONS Cycle Efficiency Net Work (out) e
= ac AT Q
p Energy (in)
{
6 a Ah SCR S/(1. K,gg)
=
=
l k
UA AT CRg (1 - K,gg)g = CRp (1 K,gg)2
=
~SUR = 26.06/r M
1/(1 K,gg)
CR /CR
=
g 0
E s
26.06 (A,7f p)
(1. K,gg)0 SyR =
M
=
(p. p)
(1. K,gg)g SUR(t)
P, 10 SDM (1
Kg)Q P
=
=
P, e */')
I W A Pwr P
=
=
g 1*/(p. p)
(1*/p)+[()-p)/A,gg) r p
r
=
p (K,gg 1)/K,gg 1*
1 x 10 5 seconds
=
l 0.1 seconds.1 l
p AK,gg/Kg.g A,gg =
=
1 l
CONVERSIONS
\\
1 10
?.21 lba 1 Curie 3.7 x 10 dps 1 kg
=
0 3.41 x 10 BTU /hr 1 hp 2.54 x 10 BTU /hr 1 Mw
=
v/5 *C + 32 1 BTU 778 ft lbf
'F
=
=
8
- C 5/9 (*F. 32)
=
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PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA13 EKAMINATION FORM A L
I,1 QUESTION:
1.
i I
The primary purpose of a pressure relief valve is to:
j t..
A.
maintain system flow.
i B.
maintain system pressure.
C.
maintain system integrity.
D.
maintain system temperature, i
f
. 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.
1
-B' increase, and the pressure on the downstream side will remain the same, l
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 a valvo backseat is to:
1' 1
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.
1 C.
provide a backup means of flow isolation in the event of primary seat leakage.
l D.
provide a backup means of flow isolation in the event of a pipe break.
FORM A Page 1 of 35
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i 9-n PRESSURIZED WATER REACT 2 CENERIC PUNDAMENTAIA EXAMINATION PORM A QUESTION:
4.
After manually positioning a motor operated valve, how is the valve actuator re engaged?
A.
Actuation of the torgue 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 FORM A Page 2 of 35
- ,c FRESSURIZED WATER REACTOR GENERIC FUNDAMENTAIS EXAMINATION FORM A
' QUESTION:
7.
If the liquid flowing through a liquid flow rate sensor contains entrained voids (gas or steam), indicated flow race will be:.
l A'.
erroneously high.
B.
erroneously low.
I C.
unaffected.
-D.
fluctuating.
QUESTION:
8.
If the equalizin6 line on a differential pressure (D/P) flow detector is opened, the flev detector indication will:
'A.
increase slightly.
l B.
decrease slightly.
C.
go to zero.
'D.
not change.
i QUESTION:
9.
Flow detectors (such as an orifice, flow nozzle, ac$ venturi tube) measure j
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
.h
.y PRESSURIZED WATfJt AEACTOR CDT.RIC PtINDAMENTALS EXAMINATION PGtM A QUESTION:
10.
The pressure differential between a reference leg and a variable leg is:
A.
DIRECTLY proportional to the height of the variable le5-B.
INVERSELY proportional to the height of the variable leg.
C.
LIRECTLY 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 le"el will:
A.
read less than actual level.
1 B.
' read greater than actual level.
l C.
equal the actual level.
D.
slowly decrease to zero.
QUESTION:
12.
l The level indication for reference leg differential pressure level instrument will fail 15 as a result of:
A.
a break on the reference leg.
a rupture of the diaphragm in the differencial pressurs cell.
l C.
the reference leg flashing to steam.
D.
a break on the variable leg.
FORM A Page 4 of 35
L_.
FRESSURIZED WATER REAC1VR GENERIC PVNDAMENTALS EXAMINATION i.
FORN A k
QUESTION:
13.
A resistance temperature detector (RTD) operates on the principle that the change in electrical resistance of:
A.
two dissimilar metals is DIRECTLY p;cportional to the temperature change measured at their j 7ction.
i B.
two dissimilar metals is INVERSELY proportional to the temperature change mes ured 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:
14.
l 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:
r l
transmitter I will read greater than transmitter II.
A.
B.
transmitter II will read greate-than transmitter I.
1 C.
transmitter I and II will read the same.
D.
it is impossibit to predict how either transmitter will respond.
t QUESTION:
15.
Scintillation detectors operate on the principle of:
~~
A.
photodisintegration.
B.
photokinesis.
C.
photomultiplication.
D.
photoionization.
FORN A Page 5 of 35
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i s' PRESSURIZED WATER REAC1TIR CENERIC FUNDAMENTALS EKANINATION FORM A 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 oppored 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 cutput. Neutron pulses are the only ones with sufficient width to yield a neutron only signal for indication use.
D.
Neutron induced currene pulses are significantly larger than those from gamma. The detector signal is appited to a circuit which' filters out the smaller gamma pulses yielding a neutron only signal for indication use.
QUESTION:
17.
"hc difference between'the setpoint and the measured parameter in an automatic f?.ow controller is called:
gain.
B.
bias.
C.
fee dback.
C.
, error.
QUESTION:
18.
t contro11or's output is typically insufficient to accurately drive a valve actuator. To overcomo this problem, a control loop normally employs:
A.
a lead / lag unit.
B.
a regulato*.
C.
a positioner.
D.
an amplifier unit.
pDRM A Page 6 of 35
(
FRESSURIZED WATTR REACTOR CENERIC FUNDANENTALS EXAMINATION
\\
FORM A 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 autematic 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-valva position.
D.
The valve can only be operated locally during this time.
l T,.
QUESTION:
20.
j What precautions must be observed when transferring a valvi controller from the automatic mode to manual mode of control?
l A.
Ensure that the proper offset is ectablished becween the automatic modo j
and manual mode.
j B.
Ensure that the valve controller oucput signals are matched between automatic mode and manual mode.
C.
Ensure that"the valve controller stabilizes in the automt. tic mode before completely transferring to the manual mode of control.
D.
Ensure that the automatic valve controller signal is increasing before i
transferring to manual mode of control.
l l
QUESTION:
21.
~~
1 l
An indication of centrifugal pump cavitation is:
1 A.
pump motor amps pegged hish.
B.
pump discharge pressure indicating rero.
C.
pump motor amps oscillating.
D.
pump discharge pressure indicating shutoff head.
1
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FORM A Page 7 of 35 t
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+ PRESSURIEED WATER REACTOR CEERIC FUNDAMENTA.TJ EXANINATION M
PORM A I
QUESTION:
22.
o 4
The, term " shutoff head" for a centrifugal pump indiente.t that it'is pumping
.t-at:'
s; 5'
A.
maximum capacity and, minimum discharge, head.'
4',
' B..
maximum capacity and maximum discharge head.
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C.
minimum capacity'and maximum discharge head.
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.D.
minimum capacity and minimum discharge head.
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v h\\q QUESTION:- 23.
-'Mrating a motor driven centUtfugal pump for extended periods of tino'with no n
flow through the pump will cause:
A.
' pump failure from overspeed.
B.'
pump failure from' overheating.
l i
C.
motor failure.from overspeed.
. e D.
motor failure from overheatir'g.
)
i 4
L QUESTION:
24.
SHUTTING the discharp valve on on operating centrifugal pump v111 cause the
~ ~
HDIQR AMPS to
_ _ and the pump DISCHAPAE PRESSURE to,,,__,
1 l'
l A.
increuse, increase 1
B.
decrease, increase l
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C.
increase, decrease l'
D.
decrease, d:terease l.
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PRESSURIZED WATER REACTOR CENERIC FUNDAMENTAIE EKAMINATION PURM A FD' QUESTION:
25.
F lIf the speed of a positive displacement pump is ir, creased, the available net i
positive suction head (NPSH) will and the probability of q
cavitation will A.
it'-ease, increase B.
decrease, wwrease Y
C.
increase, oceresse 1
decrease, increase D.
i t.
-QUESTION: V 26, 1
i Reactor coolant pump motor amps will
.if the rotor is LDCKED and the. motor speed will,
if the rotor SHEARS.
l A.
increase, increase
~
B.
increase, decrease i
l C.
decrease, increare i
i
'\\.
'D' decrease, decrease i
0-l
' QUESTION:
27.
[
If t.he generator bearings on a motor generator overh at then:
\\
'the generator voltage will incresta.
.A.
LM 1
B.
the gen 2rator windings will overheat.
q 1]q 4
s
' C.
the motor current will decrease.
A j
h)h D.
the rotor windings vill overheat.
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PRESCURIZED WATER REACTOR CENERIC FUNDAMENTAIJ EKANINATCN
- 7 FORM A 1
l QUESTION:
28.
t If the speed of a variable speed centrifugal pump is increased to cause pump
' flow rate to double, pump motor current will:
A.
. remain constant.
B.
increase two fold (double).
1 C.
increase four fold, D.
increase eight fold.
l 1
QUESTION:
29.
The starting current in an A.C. motor is significantly higher than the full load running current.because:
a.
etarting torquc.is lower than running torque.
B.
starting torque is higher than running torque.
C.
rotor current during start is higher tnan running current.
D.
rotor current durin6 start it. Iower than running current.
.l QUESTION:
30, j.
The number of starts for an electric motor in a given period of time should be L
limited because:
A.
overhosting of the windings can occur, c
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B.
excessive torque is generated during motor start.
7 C.
running current i. auch higher than starting current.
i D.
motors are normally started under full load.:nnditions.
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FORM A f
.y QUESTION:
- 31. -
Severe stress' in a mechanical componer.t, induced by a sudden, unequally j
distributed tairperature reduction is a description of:
i 1
A.
heat stress.
B.
thermal shock, i
.o C.
. thermal strain.
D.
heat strain.
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QUESTION:
32.
'fube' fouling in a heat exchanger causes heat transfer to decrease by:
j W
A.
. reducing fluid velocity on the shell side of the exchanger, j
7, o.
B.
increasing flow rate through the tube side of the axchanger, C.
re'dacing the-overe.11 (total) heat transfer coefficient.
D. increasing the everall (total) neat transfer coefficient.
I QUESTION:
33.
f g
l Borated water is flowing through the tubes of. N.at exchanger being cooled by l-L
' fresh water The shell side pressure is less than tube side pressure. What L l,l will occur as a result of a tube failure?
A.
. Depletion of borated. water inventory.
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B.
Depletion of cooling' water inventory.
i o,
j t C..
Dilution of the berated water system.
1' D.
Shell pressure will decrease.
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PRESFURIZED WATER REACTOR CDIERIC FUNDAMENTALS EXANINATION PORM A
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QUESTION:
34 Wnat is the reason for bypassing a desineralizer due to high temperature?
A.
Resins expand and restrict flow through the demineralizer.
B.
The demineralizer decontunination factor is dramatically increased.
C.
Organic compounds used as resins will decompose.
D.
The creation of preferential flowpath through the demineralizer will
- occur, t
QUESTION:
35.
In the event of a system crud burst, what adverse effect. does the crud busst i
have on demineralizer operation?
i A.
Increases pressure drop across demineralizer B.
Increases flow rate through demineralizer C.
Increases demineralizer cutlet conductivity I
D.
Increases domineralizer inlet pH QUESTION:
36.
Boron concentration in the reactor (primary) coolant system has been decreasing sten fly at approximately 10 ppa per hour while using the deborating demineralizer. 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 demineralizer 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/
1 a;
FORM A Page 12 of 35 1
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FRESSURIZED WATER REACTOR CEFERIC FUNDAMENTALS EXAMINATION I
~
PORM A j
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QUESTION:
37 To de energize a component and its associated centrol and indication circuits, the ccaponent circuit breaker should be:
A.
racked in and tagged in open position.
B.
racked in and' tagged in closed position.
C.
racked out and tagged in racked out position, j
D.
in the test position and tagged in test.
i QUESTION:
38.
To.cnsure, reliable local breaker-indication is being provided the must be reset after briaker operation.
A.
OPEN/ CLOSED mechanical flag B.-
OPEN/ CLOSED indicating li hts 6
C.
Overcurrent trip flag D.
Spring CHt.RGE/DISCHARCE flag i
1 QUESTION:
39.
A circuit breaker thermal overload device:
I A.
compares actual current to a fixed overcurrent setpoint that is equated to temperature and actuates a trip relay.
B.
when schjected 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 currant proportional to the primary current.
m
'/J FORM A Page 13 of 35
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PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EKAMINATION
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PORM A l
1 QUESTION:
40.
j j
Loss of circuit breaker control power will cause:
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.
I 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. 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.
E.
an overcurrent condition will occur on the generator.
C.
an overvoltage condition will occur between generator phases.
D.
generator undervoltage relay actuation will occur.
I 1
1 QUESTION:
42.
Which of the following statements is correct concernin5 the use of disconnect switches?
A.
Disconnects should be limited to normal load current interruption.
B.
Disconnects may be used to isolate transar wers in an unloaded network.
C.
Disconnects are similar to oil circuit breakers, but are manually operated.
D.
Disconnects must be closed with caution when under load because of possible arcing.
FORM A Page 14 of 35
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FORN A t
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.
i B._
ove rvoltage.
C.
D.
t QUESTION:
44.
. The operator has just pulled control rods and changed the effective nultipli-
. cation factor (X,gg) from 0.998 to 1.002.
The reactor is:
t A.
prompt critical B.
supercritics1 c.
exactly critical D.
suberitical-t
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-QUESTION:
45.
g.
The ratio of the number of neutrons in one generation to the number of l
neutrons.in the previous generation is the:
A.
effective multiplication factor 8.
fast fission factor-C.
neutron non leakage factor D.
neutron reproduction factor QUESTION:
46.
Reactivity is defined as the:
A.
fractional change in neutron population per generation.
l 1
B.
number of neutrons by which neutror. population changes per generation.
C.
rate of change of reactor power in neutrons per second.
3 D.
change in the number of neutrons per second that causes a fission event.
i QUESTION:
47.
l 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 significent effect on the magnitude of the stable startup rate achieved for this-addition?
A.
Prompt neutron lifetime B.
~Fual temperature coefficient C.
Average effective decay constant D.
Moderator temperature coefficient FORM A Page 16 of S.3 b
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PRESSURIEED WATER REACTOR' CENERIC FUNDAMENTAIJ EKANINATION FORN A QUESTION:
48.
f~
r 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 QUESTION:
49.
i 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 suberitical reactor.
C.
generates a sufficient neutron population to start the fission process and initiate suberitical multiplication.
D.
providea a neutron level that is detectable on the source range nuclear instrumentation.
1, L
L QUESTION:
50.
7 Why does increasing reactor coolant boron concentration cause the moderator l
temperature coefficient to become less negative?
~~
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 s
resonance escape probability.
L l-C.
Reactor coolant temperature increases result in an increase in the total i
non-leakage probability.
D.
The change in resonance escapt probability dominates the change in the i
thermal utilization factor.
1 m
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FORM A Page 17 of 35 1;
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3 v-I PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA1J IIAMINATION FORN A i
QUESTION:
$1.
Why does the fuel temperature (Doppler) coefficient becomes less negative at l
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 pataseter.
A.
An integrated, total B.
A rate of, differential C.
A differential, total D.
A total, differential l
l QUESTION:
53.
L During power operation, while changing power level, core reactivity is affected most quickly by:
l l
A.
boron concentration adjustments.
B.
power defect (deficit).
C.
D.
fuel depletion.
FORM A Page 18 of 35
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l yg PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA13 EKANINATION FORN A QUESTION:
54.
As moderator temperature' increases, the magnitude of differential rod (CEA) worth increases because:
s' A.
decreased moderator density causes more neutron leakage out of the core, B.
moderator tempernture 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:
A.
provides a more uniform differential rod (CEA) worth and axial flux 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 j
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.
The basis for the maximum power density (kw/ft) power limit is to:
A.
prevent fuel clad scit.
B.
prevent fuel pellet melt.
C.
limit bulk coolant temperature.
D.
prevent nucleate boiling.
FORN A Page 19 of 35
- s PRESSURIEED WATER REAC1DR CENERIC FUNDAMENTALS EKAMINATION FORN A QUESTION:
57.
I i
The control rod insertion limits are power level dependent because the magnitude'of:
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, i
QUESTION:
58.
Fission products that have substantial neutron capture cross sections are:
A.
excited fission products.
B.
fission product daughter.
i C.
radioactive fission products.
I D.
fission product poisons.
QUESTIOJ:
59.
. Following 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, j
C.
remain the same because the decay of Iodine and Xenon balknee each other
- out, l
D.
decrease immediately, then slowly increase due to the differences in the j
half-lives of Iodine and Xenon.
FORN A Page 20 of 35
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PRESSURIZED WATER REACTOR CDIERIC WNDAMENTAIE EKAMINATION 3
PORN A e
QUESTION:
60.
Following a reactor trip from sustained high power ' operation, the major Xenon 135 removal' process is:
A.
ion exchange.
B.
beta decay.
C.
neutron capture.
I D.
alpha decay.
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 velue will-A.
be twice the 50 percent value.
B.
be less than twice the 50 percent value.
1 C.
be more than twice the 50 percent value.
D.
remain the same since it is independent of power.
QUESTION:
62.
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.
B.
' Xenon override.
I C.
Xenon burnup.
1 i
D.
Xenon oscillation.
i 1
i i
1
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FORM A Page 21 of 35
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QUESTION:
63.
A reactor that has been operating at rated power for about two weeks reduces j
power to 50 percent. Xe 135 will reach a new equilibrium condition in j
hours.
4 l
\\
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 /> 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 /> 5
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 rero and requires excessive amounts of water to dilute.
B.
The differential boron worth has decreased below its useable point.
l C.
The boron in the coolant has been depleted due to neutron absorption, D.
"Coastdown" is preferred due to fuel conditioning limitations.
L QUESTION:
65.
(
)
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 E
the first doubling is added again?
~~
.A.
Count rate will increase s.:<j. v l
L B.
Count rate will double.
L l
C.
The reactor will remain suberitical.
l.
l D.
The reactor will be critical or slightly supercritical.
l' l
l.
r FORM A Page 22 of 35 i
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PRESSURIZED WATER REACTOR CENERIC RJNDAMENTALS EXAMINATION l
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. PORM A j
1
-QUESTION:
66.
4 In a reactor with a source, a non changing neutron flux over a few minutes is indicative of criticality or i
A.
the point of adding heat.
B.
supercriticality.
C, suberiticality, j
D.
equilibrium suberitical count rate.
b QUESTION:
67.
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 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.
D, one control rod (CEA) remains fully inserted during the approach to criticality.
s QUESTION:
68.
~-
Withk[f-0.985,howmuchreactivitymustbeaddedtomakethereactor i
critica A.
1,480 pcm'(1.48% delta-k/k)
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) s FORM A Page 23 of 35
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PRESSURIZED WATER REACTOR CENERIC WNDAMENTALS EXAMINATION
..f A QUESTION:
_69.
(
If, during a reactor startup, the startup rato is constant and positive l'
without any further reactivity addition, then the reactor is:
A.-
critical.
B.
supercritical.
C.
suberitical.
D.
prompt critical.
QUESTION:
70.
Civan 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 y
I reactivity effect.
C.
The cecrease in fuel temper ture will begin to create a negative
~
p reactivity effect'.
D.
The increase in fuel temperature will begin to create a negative reactivity effect.
QUESTION:
71.
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 D.
90 FORM A Page 24 of 35 l
PRESSURIZED WATER REACTOR CENERIC PTNDAMENTAIJi EIAMINATION PORM A
.:e
QUESTION:
72.
' 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.
C.
an increase in core life.
D.
a reduction in the effect of resonance capture.
i l
1 1
a I
i l
l FORM A Page 25 of 35 1
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PRESSURIZED WATER REACTOR CENERIO FUNDAMENTALS EKAMINATION FORM A QUESTION:' 73.
- An' atmospheric pressure of 15 psia equsis:
A-30 psig.
B.
15 psig.
' C.
5 psig.
D.,
O psig.
QUESTION:
74.
, Condensate depression is defined as:
A.-
cooling the condensate below its saturation temperature.
l B.
maintaining the condensate at a constant temperature throughout the system.
C.
ensuring that the condensate is below the level of the hotwell pumps.
~
D.
cooling the condensate to the point of saturation.
QUESTION:
75.
What is the reactor coolant system subcooling for Tave - 400'F and pressurizer pressure - 1,000 psia?
A.
75'F l
B.
100'F C.
125'?
D.
145'F I
L
'l, FORM A Page 26 of 35
+
PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION FORN A p,.
QUESTION:. 76.
The plant is maintained at 2,000 psia with a pressurizer temperature of 636'F.
e
. A pressurizer 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 i
. 3 relief valve?
A.
280'F B.
240'F
?
C.
190'F D.
170'F QUESTION:
77, s
Overall plant efficiency will' DIClL]ESE if:
A.
the steam quality is increased by removing moisture from the steam prior to entering the turbine.
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.
D.
the temperature of the steam at the turbine inlet is decreased.
QUESTION:
78.
The possibility of~a water hammer is MINIMIZED by:
A.
changing valve positions as rapidly as possible.
l.
B.
starting centrifugal pumps with the discharge valve fully open.
l C.
starting positive displacement pumps with the discharge valve closed.
i D.
ventin6 systems prior to starting centrifugal pumps.
l.
?
l FORM A Page 27 of 35 1
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PRESSURIZED WATER REAC1OR CENERIC MINDAMENTAIS EKANINATION FORN A QUESTION:
79.
I j
i.
Cavitation in an operating pump may be caused by:
A.
lowering the suction temperature, f
B.
throttling the pump suction valve.
j C.
throttling the pump discharge valve.
l D.
increasing the pump discharge pressure.
QUESTION:
80.
The piping system pressure change caused by suddenly stopping fluid flow is referred to as:
s A.
cavitation.
B.
shutoff head.
C.
D.
flow head.
' QUESTION:
81.
i 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.
~~
B.
greater than actual mass flow rate with a decrease in temperature of the fluid.
.l C.
less.than actual mass flow rate with a decrease in temperature of the flaid.
D.
less than actual mass flow rate with an increase in temperature of the fluid.
FORM A Page 28 of 35
e PRESSURIZED WATER REACTOR CENERIC IVNDAMENTALS EXANIMATION FORM A t
QUESTION:
82.
.i l
Operating two pumps in parallel instead of operating a single pump will result L
in:
L 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 flew rate.
D.
a decrease in system head and a large increase in flow rate.
QUESTION:
83.
Excessive amounts of entrained gases passing through a single phase (liquid) heat exchanger is UNDESIRABLE because:
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.
c
. QUESTION:
84.
In a two loop pressurized water reactor, feedwater flow to each steam generator is 3.3 x 10 lbm/hr at an enthalpy of 419 BTU /lbm. The steam exiting each steam generator is at 800 psia with 100g 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 FORM A Page 29 of 35
w PRESSURIZED WATER REACTOR CENERIC TUNDAMENTALS EKAMINATION FORM A 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.
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 3
reduces coolant flow in that aree 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 i
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
L 1
l~
QUESTION:
87.
What parameter change would move the plant farther away from the critical heat i
flux?
l l
A.
Decrease pressurizer pressure l
B.
Decrease reactor coolant flow L
C.
Decrease reactor power l
D.
Increase reactor coolant temperature FORM A Page 30 of 35
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FORM A
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QUESTION:
88.
f-Film boiling is:
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.
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 a fuel rod.
C.
the core thermal power divided by the total reactor coolant mass flow rate.
D.
the number of cociant channels that have reached DNB divided by the number of coolant channels'that are subcooled.
QUESTION:
90.
f
.The reactor coolant subcooling margin will be PIRECTLY REDUCED by: (Evaluate L
each change separately.)
j h
l A.
increased pressurizer pressure.
B.
increased pressurizer level.
C.
increased reactor coolant flow.
L D.
increased reactor coolant temperature.
1.
b, l'
I' L
FORM A Page 31 of 35
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PRESSURIZED WATER REACTOR CDIERIC FUNDAMENTALS EKAMINATION FORM A
-QUESTION:
91, i
Maximizing the elevation difference between the core thermal center and the steam generator thermal centers and minimizin6 flow restrictions in the reactor coolant system (RCS) piping are plant designs to:
]
i A.
minimize the reactor coolant system volume.
1 B.
maximize the reactor coolant system flow rate during forced circulation.
]
C.
ensure a maximum RCS loop transit time.
D, ensure RCS natural circulation flow can be established.
QUESTION:
92.
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 increhse.
B.
time after reactor trip.
C.
steam generator level increase.
D.
steam generator pressure decrease.
1 I
QUESTION:
93.
1 L
If departure from nucleate boiling (DNB) is reached in the core, the surface temperature of the fuel clad will:
A.
increase rapidly.
l B.
decrease rapidly.
l C.
increase gradually.
D.
decrease gradually.
FORM A Page 32 of 35
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-PRESSURIZED WATER REACTOR CENERIC FUNDAMENTAIE EKANINATION FORN A-rs QUESTION:
94.
1 If' the reactor is operated within core thermal limits, then:
I A.
plant tharmal efficiency is optimized.
B.
' fuel cladding integrity is ersured.
i C.
Pressurized thermal shock will be prevented.
.D.
Reactor vessel thermal stresses will be minimized.
1 t
QUESTION:
95.
Fast neutron Irradiation of the reactor vessel results in stresses within the vessel metal, thereby the Nil Ductility Transition Temperature.
A.
increased, increasing B.
increased, decreasing C.
decreased, increasing D.
decreased, decreasing
. QUESTION:
96.
The likelihood of brittle fracture' failure of the reactor vessel is REDUCED by:
A.
increasing vessel age.
L l-B.
reducing vessel pressure.
C.
reducing vessel temperature.
D.
reducing gamma flux exposure.
l l
i 1
l-l l
1.
FORN A Page 33 of 35
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IE PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION 1
FORM A W
QUESTION:
97.
j 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.
e QUESTION:
98.
The nil ductility temperature is that temperature:
A.
below which the probability of brittle fracture significantly increases.
l 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 1 fracture stress, a
L 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 overprecsurization from a low temperature, low pressure condition.
FORM A Page 34 of 35
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. QUESTION:
100.
L During a severe overcooling transient, a major concern to the operator is:
t-I-
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.
t l
t l~
4 FORN A Page 35 of 35
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ANSNER KEY PWR GFE (FORM B) 1.
D.
26.
A.
51.
B.
76.
A.
2.
A.
27.
A.
52.
B.
77.
D.
3.
D.
28.
D.
53.
D.
78.
A.
4.
B.
29.
C.
54.
A.
79.
D.
5.
D.
30.
D.
55.
D.
80.
C.
6.
D.
31.
A.
56.
D.
81.
B.
82.
D.
7.
B.
32.
D.
8.
C.
33.
B.
58.
A.
83.
A.
9.
C.
34.
B.
59.
B.
M i
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.
L 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.
^^
O.
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.
25.
B.
50.
C.
75.
C.
100.
C.
Pressurized Water Reactor Generic Fundamentals Examination administered October 4, 1989. Questions 42, 57 and 84 were deleted.
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UNITED STATES NUCLEAR REGULATORY COMMISSION PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION Please Print:
Name:
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.
i SECTION Questions
% of Total Score THERMODYNAMICS 1 - 28 COMPONENTS 29 - 71 REACTOR THEORY 72 - 100 l-TOTALS 100 l
l l
L l
All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature L
FORM B f
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B 9
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i' RULES AND CUIDELINES FOR THE CENERIC TUNDAMENTALS EXAMINATION i
During the administration of this examination the following rules apply:
1 (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 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 l
and scrap paper used during the examination.
(12) Af ter turning in your examination materials, leave the examination area, as defined by the examinar. If after leaving you are found in the l
examination area while the examination is in progress, your examination l
may be forfeited.
1 i
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[d SENER.IC FUNDAMETALS EEMtINATION SECTICM lf SQUATICIts AND CONVERSIONS MMfDOUT SHEET EIGAT10ltS 1
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i PRESSURIZED WATER REACTOR GDIERIC PUNDAMENTAIE EEAMINATION I
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PORM &
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QUESTION:- 1.
An atmospheric pressttre of 15 psi.1 equals:
?
/
I A.
30 psig.
B.
15 psig.
i C.
5 psig.
D.
O psig.
, QUESTION:
2.
b Condensate depression is defined as:
i
'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 hotwell pumps.
.D.
cooling the condensate to the point of saturation.
t QUESTION:
3.
t What is the reactor coolant system subcooling for Tave - 400'F and pressurizer pressure - 1,000 psia?
A.
75'F B.
100'F l
I C.
125'T r
D.
145'T l
l l.
l l
l t:
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l' FORM B Page 1 of 34 l
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' 4 N
PRESSURIZED WATER REAC'IOR CENERIC MINDAMENTAIE EIANINATION
- FORM B l
,j.
' QUESTION':
4.-
i
'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 temperature of the fluid downstream of the j
relief valve?
j A.
280'F l
B.
240'F C.
190*F t
D, 170'T QUESTION:
5.
Overall plant efficiency will DECREASE if:
i A.
'the steam quality is increased by removing moisture from the steam prior to ente-ing the turbine.
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.
D, the temperature of the steam at the turbine inlet is decreased.
QUESTION:
6.
The possibility of a water hammer is MINIMIZED by:
A.
changing valve positions as rapidly as possible.
B.
starting centrifugal puaps with the discharge valve fully open.
C.
starting positive displacement pumps with the discharge valve closed.
D.
venting systems prior to starting centrifugal pumps.
FORM B Page 2 of 34 f'
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FRESSURIZED WATER REACTOR CENERIC PMIDMODITAIA EXAMINATION PORM B p
QUESTION:
'7.
Cavitation in an operating pump may be caused by:
,i A.'
lowering the suction temperature.
B.
' throttling the pump suction valve.
C.
throttling the pump discharge valve.
D.
increasing the pump discharge pressure.
QUESTION:
8.
The piping system pressure change caused by suddenly stopping fluid flow is referred to as:
A.
cavitation.
B.
shutoff head.
C.
D.
flow head.
QUESTION:
9.
If a flow measuring instrument is BQI density compensated, then indicated mass flow rate will be:
A.
the same as actual mass flow rate with a change in temperature of the-l fluid.
L B.
greater than actual mass flow rate with a decrease in temperature of the l
fluid.
l j
C.
loss than actual mass flow rate with a decrease in temperature of the 1
I fluid.
I D.
less than actual mass flow rate with an increase in temperature of the i
fluid.
l 1:
l l
I FORM B Page 3 of 34
i
'c L,
PRESSURIZED WATER REAC'ICR CENERIC RJNDAMENTALS EKANINATION i
i L
FORM B QUESTION:
10.
J Operating two pumps in parallel instead of operating a single pump t
will resultin:
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 f.n flow rate.
QUESTION:
11.
Excessive amounts of entrained gases passing through a single phase (liquid) heat exchanger is UNDESIRABLE because:
A.
flow blockage can occur in the heat exchange.r.
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.
c QUESTION:
12.
In a two loop pressurized water reactor, feedwater flow to each steam generator is 3.3 x 10 lbm/hr at an enthalpy of 419 BTU /lbm. 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?
t A.
3,411 MWt B.
2,915 MWt s~
C.
2,212 MWt D.
1,509 MWt l~
FDRM B Page 4 of 34 i
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a PRESSURIZED WATER REACTOR CENERIC PUNDAMENTALS EKAMINATION y
FORM B
. QUEST 70N:
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.
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 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
QUESTION:
15.
What parameter change would move the plant farther away from the critical heat L
flux?
l A.
Decrease pressurizer pressure B.
Decrease reactor coolant flow C.
Decrease reactor power D.
Increase reactor coolant temperature FORM B Page 5 of 34
e.
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h PRESSURIZED WATER REACTOR CMERIC MINDAMENTALS EIAMINATION FORM B i
QUESTIONi. 16.
Film boiling is:
A.
heat transfer through a vapor blanket that covers the fuel cladding.
3
'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:
17.
l The departure from nucleate boiling ratio (DNBR) is defined as:
i.'
I 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.
i C.
the core thermal pwer 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.
I QUESTION:
18.
The reactor coolant subcooling margin will be DIRECTLY REDUCED by: (Evaluate i
each change separately.)
A.
increased pressurizer pressure.
1 L
B.
increased pressurizer level.
C.
' increased reactor coolant flow.
D.
increased reactor coolant temperature, t
r l
FORM B Page 6 of 34
i
.f PRESSURIEED WATER REACTOR CENERIC FUNDAMENTALS EEANIMATION-l FORM B-i e
QUESTION:
19.
r Maximizing the elevation difference between the core thermal center and the-steam generator thermal centers and minimizing flow restrictions in the reactor coolant system (RCS) piping are plant designs to:
A.
minimize the reactor coolant system volume, i
B.
maximize the reactor coolant system flow rate during forced circulation.
C.
' ensure a maximum RCS loop transit time.
4 D.
ensure RCS natural circulation flow can be established.
QUESTION:
20.
k With the RCS subcooled and all RCPs stopped, the natural circulation flow rate will HQI be affected by an increase in the:
A.
rear. tor coolant pressure increase.
'B.
time after reactor trip.
C.
steam generator level increase.
D.
steam generator pressure decrease.
QUESTION:
21.
i r
If departure from nucleate boiling (DNB) is reached in the core, the surface temperature of the fuel clad will:
l l
A.
increase rapidly.
p B.
decrease rapidly.
l C.
Increase gradually.
D.
decrease gradually.
L FORM B Page 7 of 34 i
a
. ~
4
c FRESSURIEED WATER REACTtlR CINERIC IUNDMtENTA13 EKANIMATION PORN B j.'
I QUESTION:
22.
i k, If the reactor is operated within core thermal 1!.mits, then:
U A.
plant thermal efficiency is optimized.
i B.
fuel cladding integrity.is ensured.
)
i i
C.
pressuriced thernal shock will be prevented.
i L
i D.
reactor vessel thermal stresses will be minimized, j
i t.
1 l
QUESTION: 23.
Fast neutron irradiation of the reactor vessel results in stresses l
within the vessel metal, thereby the Nil. Ductility Transition l
Temperature.
A.
increased, increasing l
B.
increased, decreasing 1
C.-
decreased, increasing D.
decreased, decreasing i
l QUESTION: 24 l
l l
The likelihood of brittle fracture failure of the reactor vessel is REDUCED by-A.
increasing vessel age.
i
~~
B.
reducing vessel pressure.
i C.
reducing vessel temperature.
i L
D.
reducing gamma flux exposure.
1 I
l l
l l
l l
1 l
l FORN B Page 8 of 34 i
h.
PRES $URIFE.D WATFJt REACTt* CENERIC FUNDMENTA1J EIANIMATION FORN &
i QUESTION:- 25.
I Pressure stress on the reactor vessel wall is-
')
A.
compressive across the entire wall.
1 B.
tensile across the entire wall.
C.
tensile at the inner wall, compressive at'the outer wall.
l
\\
D.
compressive at the inner all, tensile at the outer wall.
l 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.
C.
below which the probability of plasuc deformation significantly increases.
D.
below which the yield stress of the metal is higher than the critical fracture stress.
QUESTION:
27.
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 condittori.
QUESTION:
28.
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 fractura of the reactor vessel.
FORM B Page 9 of 34 A-
E.
PRESSURIEED WATER REACTOR CENERIC PUNDMG3fTALS EKAMINATION FORM &
(
- QUESTION:
29.
The primary purpose of a pressure relief valve is to:
{
A.
maintain system flow, f
B.
maintain system pressure.
)'
C.
maintain system integrity.
D.
maintain system terperature.
c i
I QUESTION:
30.
I When a discharge valve is opened to atmosphere, the pressure on the upstream t
side of the valve will:
A.
remain the same, and the pressure on the downstream side will increase, i
B.
increase, and the pressure on the downstream side will remain the same.
C.
remain the same, and the pressure on the downstrean side will decrease.
D.
decrease, and the pressure on the devnstream side will remain the same.
QUESTION:
31.
The function of a valve backseat is to:
i r
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 I
of valve repacking.
t C.
provide a backup means of flow isolation in the event of primary seat leakage.
l D.
provide a backup means of flow isolation in the event of a pipe break.
I i
l l
FORM B Page 10 of 34 l
l l
l
i FRESSURIZED WATER REAC1CR CENERIC WNDAMENTAIE ERAMINATION
)
FORM B QUESTION:
32, j
After manually positioning a motor operated valve, how is the valve actuator 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 D.
Actuation of the valve actuator noter in either the open or close j
direction QUESTION:
33.
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.
l B.
in the closed direction using normal force.
l 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:
34 j
Density compensation is used in flow instruments to change to A.
mass flow rate, volumetric flew rate B.
volumetric flow rate, mass flow rate I
C.
fluid pressure, volumetric flow rate c
l D.
differential pressure, mass flow rate l
FORM B Page 11 of 34 1
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MtESSURIZED WATER RE/.C1VR CENERIC FUNDAMBtTAIJ ERANIMATION
{
PORN 8 L
i QUESTION:
35.
1 If the liqu!d flowing through a liquid flow rate sensor contains entrained voids (gas or steam), indicated flow rate will be:
j 1
A.
erroneously high.
J B.
erroneously low.
C.
unaffected.
l i
t D.
fluctuating, QUESTION:
36, i
If the equalizing line on a differential pressure (D/P) flow detector is l
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 norr.le, and venturi tube) neasure flow rate using the principle that flow rate is:
I l
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.
l l
D.
INVERSELY proportional to the square root of the differential pressure.
i l
i l
t
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l l
PORM B Page 12 of 34 l
l l
I
I PRESSURIZED WATER REACTOR CENERIC MINDAMENTA13 EEANINATION PORN 5 QUESTION:
38.
The pressure differential between a reference leg and a variable leg is:
i A.
DIRECTLY proportional to the height of the variable leg.
l B.
INVERSELY proportional to the height of the variable leg.
C.
ElRECILY proportional to the density of the reference leg.
i D.
IdVERSELY prcportional to the temperature of the reference leg.
t i
QUESTION:
39.
I If the reference leg of a differential pressure level indicator experiences i
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 tc zero.
QUESTION:
40.
The output for a reference leg differential pressure level instrument will fail LQW as a result of*
A.
a break on the reference leg.
i B.
a rupture of the diaphragm in the differential pressure cell.
C.
the referenca leg flashing to steam.
D.
a break on the variable leg.
1 1
FORN B Page 13 of 34
c Q
e FRESSURIZED WATER REACTOR GENERIC MINDAMENTA12 ERAMINATION FORM 5 QUESTION:
41.
A resistance temperature detector (RTD) operates on the principle that the i
change in electrical resistanne of:
A.
two dissimilar metals is DIRECTLY proportional to the temperature change measured at their junction.
B.
tvo 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, i
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:
j A.
transmitter I will read greater than transmitter II.
B.
transmitter 11 will read greater than transmitter I.
1 C.
transmitter I and II will read the same.
D.
it is impossible to predict how either transmitter will respond.
l QUESTION:
43.
Scintillation detectors operato on the principle of:
A.
photodisintegration.
B.
photokinesis.
C.
photomultiplication.
D.
photoionization.
i i
FORM B Page 14 of 34
PRESSURIEED WATER REAC10R CDIERIC PVNDAMENTALS EXAMINATIOlt 70RM B QUESTION: 44 A BF3 proportional counter detects both neutrons and gammas. Which of the following best describes the nethod 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 pulsus are of insufficient vidth to generate a significant log level amplifier output. Neutron pulses are the only ones with sufficient vidth 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:
45.
The difference between the setpoint and the measured parameter in an automatic flow controller is called:
A.
gain.
B.
bias.
C.
feedback.
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.
t positioner.
D.
an amplifier unit.
FORM B Page 15 of 34
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PRESSUstIZED WATER REACTOR CENERIC IVNDAMENTAIA EXAMINATION FORM B l
QUESTION:
47.
1 l
i Why must an operator pay particular attention to auto / manual valve controllers j
left in the manual mode?
A.
The manual valve control is usually not stable compared to the automatic node.
i B.
The valve position will no longer respond to changes in system parameters, i
C.
The controlled parameters will no longer be controlled by the valve
- position, q
D.
The valve can oriy be operated locally during this time.
QUESTION:
48.
1 What precautions must be observed when transferring a valve controller from i
the automatic mode to manual mode of control?
1 A.
Ensure that. the proper offset is established between the automatic mode and manual mode.
)
i B.
Ensure that the valve controller output signals are matched between automatic mode and manual mode.
I C.
Ensure that the valve controller stabilizes in the automatic i
mode before completely transferring to the manual mode of l
control.
D.
EnsuTe that the automatic valve controller signal is increasing before transferrirg to manual mode of control, f
i QUESTION:
49.
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.
PORM B Page 16 of 34
4.
o PRES $URIEED WATER REACitlR CENERIC ItlNDAMENTA1A EEAN1 NATION f
FORM B QUESTION:
$0.
j The ters
- shutoff head" for a centrifugal pump indicates that it is pumping at:
j i
A.
maximum capacity and minimum discharge head, j
B.
maximum capacity and maxinum discharge head.
C..
minimum capacity and maximas discharge head.
l D.
ainimum capacity and minimus discharge head.
t 1
QUESTION:
$1.
t Operating a motor driven centrifugal pump for extended periods of time with no 7
flow through the purp will cause:
A.
pump failure from overspeed.
B.
pump failure from overheating, j
C.
motor failure from overspeed, i
D.
motor failure from overheating.
i QUESTION:
$2.
SHUTTING the discharge valve on an operating centrifugal pump will cause the MOTOR AMPS to and the pump DISCHARGE PRESSURE to A.
increase, increase l
B.
decrease, increase l
~
C.
increase, decrease D.
decrease, decrease l
t PORM B Page 17 of 34 m
,wn n
-+
e-PRESSURIZED WATER REACTOR CENERIC MINDAMENTAIJ IIANINATION FORN B p
[.
QUESTION:
53.
' If the speed of a positive displacement pump is increased, ti.e available net i
positive suction head (NPSH) will and the probability of cavitation will A.
increase, increase B.
decrease, decrease f
C.
increase, decre ase D.
decrease, increase i
QUESTION:
54.
Reactor coolant pump motor anps will if the rotor is LDCKED and the notor speed will if the rotor SHEARS.
A.
increase, increase l
t B.
increase, decrease C.
decrease, increase i
i D.
decrease, decrease e
QUESTION:
55.
If the generator bearings on a motor generator overheat then:
[
A.
the generator voltage will increase.
i i
B.
the generator vindings will overheat.
C.
the motor current will decrease.
l D,
the motor windings will overheat.
1 t
1
[
i FORN B Page 18 of 34
o PRESSURIEED WATER REACTOR CENERIC WNDANDfTALS EKAkINATION
]
FORM B QUESTION:
$6.
- o I
[
If the speed of a variable speed centrifugni pump is increased to cause pump K
flow rate to double, pump motor current will:
)
A.
remain constant.
3 B.
increase two fold (double).
}
C.
increase four fold.
t O.
increase eight fold, f
i QUESTION:
$7.
The starting current in an A.C. motor is significantly higher than the full load running current because:
l i
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.
l 5
D.
rotor current during start is lower than running current.
t
[
QUESTION: 58.
The number of starts for an electric motor in a given period of time should be f
limited because:
j A.
overheating of the windings can occur.
B.
excessive torque is generated during motor s tart.
~
C.
running current is much higher than startinl; current, i
D.
motors are normally started under full load conditions.
l i
i i
FORM B Page 19 of 34
~ __
o PRESSURIEED WATER REACTOR GENERIC RINDAMENTALS EIANIMATION PORN B j
QUESTION:
59.
Severe stress in a mechanical component, induced by a sudden, unequally distributed tenperature reduction is a description of:
3 l
A.
heat stress.
B.
thernal shock.
i 1
C.
thermal strain.
D.
heat strain.
{
i i
QUESTION:
60.
l Tube fouling in a heat exchanger causes heat transfer to decrease by:
l A.
reducing fluid velocity on the shell side of the exchanger.
i i
B.
increasing flow rate through the tube side of the exchanger.
C.
reducing the overall (total) heat transfer coefficient, i
D.
increasing the overall (total) heat transfer coefficient.
i
(
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.
t 1
i FORM B Page 20 of 34
a,
PRESSURIEED ilATER REAC1DR CDmRIC FUNDAIGNTALS EKAMINATION j
FORM B j
QUESTION:
62.
k' hat is the reason for bypassing a demineralizer 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 vill decompose.
~
D.
The creation of preferential flowpath through the demineralizer will
)
- occur, j
QUESTION:
63.
In the event of a system crud burst, what adverse effect does the crud burst have on demineralizer operation?
l A.
Increases pressure drop across demineraliger B.
Increases flow rate through domineralizer C.-
Increases demineralizer outlet conductivity t
D.
Increases demineralizer inlet pH l
QUESTION:
64 Boron concentration in the reactor (primary) coolant system has been de-creasing steadily at approximately 10 ppm per hour while using the deborating i
demineralizer. After several hours, the rate decreases to 2 ppe per hour.
khat is a possible cause for the change in deboration rate?
A.
Temperature of the coolant passing through the domineralizer has decreased.
B.
pH of the coolant has increased significantly.
1 C.
Flow through the deborating resins has increased sharply.
l l
D.
Deborating resins have bscome boron saturated.
l' i
l l
l l
l FORM B Page 21 of 34 l
1
c o
PRESSURIEED WATER REACTVR CDIERIC FUNDAMENTALS EIANIMATION 6
PORN B QUESTION:
65.
To de energire a component and its associated control and indication circuits, the component circuit breaker should be:
A.
racked in and tagged in open position.
B.
racked in and tagged in closed position, j
i C.
racked out and tagged in racked out position.
D.
in the test position and tagged in test.
QUESTION:
66.
To ensure reliable local breaker indication is being provided the j
must be reset after breaker operation, j
A.
OPEN/ CLOSED mechanical flag l
B.
OPEN/ CLOSED indicating lights C,
Overcurrent trip flag D.
Spring CHARGE /DISCHAhGE flag i
?
QUESTION:
67.
l A circuit breaker thermal overload device:
l A.
compares actual current to a fixed overcurrent setpoint that is equated to temperature and actuates a trip relay.
c i
~~
B.
when subjected to high current, overheats and sctuates a circuit-l interrupting device.
C.
senses operating equipment temperature and trips protective circuits at preset limits.
C.
is an induction coil that produces a secondary current proportional to the primary current.
k L
FORM B Page 22 of 34
,m----,-
,,n--.
o PRESSURIEED WATER REACTOR CENERIC FUNDAMENTA13 EXAMINATION
]
FORN B QUESTION:
68.
1 Loss of circuit breaker control power will cause' A.
breaker line voltage to be zero regardless of actual breaker position, j
B.
the remote breaker position to indicate closed regardless of actual breaker position.
C.
inability to operate the breaker locally and remotely.
l D.
failure of the close spring to charge following local tripping of the
- breaker, i
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.
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.
i D.
generator undervoltage relay actuation will occur.
I i
QUESTION:
70.
4 Vhich of the following statements is correct concerning the use of disconnect switches?
A.
Disconnects should be limited to normal load current interruption, i
B.
Disconnects may be used to isolate transformers in an unloaded network.
C.
Disconnects are similar to oil circuit breakers, but are manually operated.
-D.
Disconnects must be closed with caution when under load because of possible arcing.
FORM B Page 23 of 34
o PRESSURIEED nlATER REACTOR CENERIC FUNDAMENTALS EIANINATION FORM B QUESTION:
71.
l closing a Sanerator output breaker with the generator frequency much less than grid frequency will cause the generator to trip on:
i A.
reverse power.
B.
ove rvoltage.
C.
D.
I 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:
A.
prompt critical B.
supercritical
?
C.
exactly critical i
D.
suberitical l
I l
i 1
1 f
1 l
FORM B Page 24 of 34 i
r
~
I l
o-i.
PRES;iURIEED WATER REACitlR CENERIC PVNDMGNTALS EEANIMATION i
PORM B I
QUESTION:
73.
The ratio of the number of neutrons in one generation to the number of E
neutrons in too previous generation is the:
i.
l A.
. effective multiplication factor B.
fast fission factor C.
neutron non Itakage factor j
i D.
neutron reproduction factor i
t t
QUESTION:
74.
Reactivity is defined as the:
A.
fractional change in neutron populaticn per generation.
B.
number of ncutrons 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 delayed neutron fraction. Which of the following will have a significant source (startup) range The amount added is less than the average effective 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.
Hoderator temperature coefficient FORM B Page 25 of 34
a-o s'
FRESSURIEED WATER REACTOR GENERIC FUNDAMENTA1A EKANIMATION O-FORM B QUESTION: 76.
Over core life the production of plutonium isotopes with delayed neutron fractions than uranium delayed neutron fractions will cause reactor power transitnts to be near the end of core life.
A.
less, faster B.
less, slower C.
greater, faster-D.
greater, slower QUESTION:
77.
An installed neutron source:
A.
sain*.ains the production of neutrons high enough to allow the reactor to echieve criticality.
B.
provides a means to allow reactivity changes to occur in a suberitical 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:
78.
Why does increasing reactor coolant boron concentration cause the moderator temperature coefficient to become less negative?
I A.
Reactor coolant temperature increases result in a larger increase in the i
thermal utilization factor.
B.
Reactor coolant temperature increases result in an increase in the resonance escape probability.
l C.
Reactor coolant temperature increases result in an increase in the total non leakage probability.
l D.
The change in resonance escape probability dominates the change in the L
thermal utilization factor.
l l
l l
FORM B Page 26 of 34 l
Q PRESSURIZED WATER REACTOR CElNERIC PWDAMDITALS EXAMINATION
[
FORM B 1
l QUESTION:
79.
I k'hy does the fuel temperature (Doppler) coefficient becomes less negative at I
higher fuel tenperaturest l
t A.
As reactor power increases, the rate of increase in the fuel temperature
[
diminishes.
t B.
Neutrons penetrate deeper into the fuel, resulting in an increase in the
[
fast fission factor.
r 1
C.
The amount of self. shielding increases, resulting in less neutron l
absorption by the inner fuel, j
i D.
The amount of Doppler broadening per degree change in fuel temperature diminishes.
l QUESTION:
80.
i A reactivity coefficient measures change while a reactivity defect (deficit) seasures 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 i
D.
a total, differential QUESTION:
81.
~~
During power operation, while changing power level, core reactivity is affected most quickly by:
A.
boron concentration adjustments.
i B.
power defect (deficit).
C.
D.
fuel depletion.
{
FORM B Page 27 of 34
G O
l*
PRESSURIEED WATER REACTOR CDikRIC FVNDANDiTALS IIANINATION FORN &
QUESTION: 82.
As moderator temperature increases, the sagnitude of differential rod (CEA) vorth increases because:
A.
decreased moderator density causes more neutron leakage out of the core.
B.
moderator tenperature coefficient decreases, causin8 decreased corpetition.
C.
fuel temperature increases, decreasing neutron absorption in fuel.
D.
decreased moderator density increases neutron migration length.
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) vorth 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.
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.
QUESTION:
84.
The basis for the maximum power density (kv/ft) power limit is to:
l A.
prevent fuel clad melt.
l l
B.
prevent fuel pellet nelt.
l C.
limit bulk coolant temperature.
l l
D.
prevent nucleate boiling.
l l
l FORM B Page 28 of 34
O C
PRESSURIZED WATI:R REACTOR CENE3 TIC FUNDAMENTALS EKANIMATION 4
FORM B QUESTION:
85.
The control rod insertion limits are power. level dependent because the nagnitude of:
A.
control rod worth decreases as power increases.
B.
power defect increases as power increases.
C.
Doppler (fuel tenperature) 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.
radioacti e fission products.
D.
fission product poisons.
QUESTION:
87.
Following a reactor trip from sustained high power operation, Xenon.135 concentration in the reactor vill:
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
- D FRESSURIEED WATER REAC1tlR CENERIC FUNDAMENTALS ERAMINATION
+
i FORM B l
QUESTION:
88.
Following a reactor trip from austained high power operation, the major Xenon 135 removal process is:
i A.
ion exchange.
l i
B.
beta decay.
C.
neutron capture.
I D.
alpha decay.
f QUESTION:
89.
A reactor,has been operating at 50 percent power for 7 days when power is l
ranped to 100 percent over a four hour period. The new equilibrius Xenon
[
value vill:
A.
be twice the 50 percent value.
S.
be less than twice the 50 percent value.
C.
be more than twice the $0 percent value.
D.
remain the same since it is independent of power, f
f i
I QUESTION:
90.
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:
L A.
Xenon peaking.
i B.
Xenon override.
I i
i C.
Xenon burnup.
I D.
Xenon oscillation.
i l
1 t
PORM B Page 30 of 34 l
t
G FRESSURIEED WATER REACTOR CINERIC FUNDAMENTALS EKANIMATION
(
PURN &
L L
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.
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:
92.
The reactor is near the end of its operating cycle.
In order to stay critical, power and tenperature have been allowed to "coastdown.' Why is boron no longer uced to compensate for fuel depletion?
A.
Boron concentration approacht<a zero and requires excessive amounts of water to dilute.
B.
The differential bcron 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 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.
B.
Count rate will double.
C.
The reactor will remain suberitical.
D.
The reactor will be critical or slightly supercritical.
FORM B Page 31 of 34
o FRESSURIEED WATER REACTOR CENI3t1C FUNDMUNTA1A ERANIMATICII PORM &
QUESTICM:
94.
In a reactor with a source, a non changing neutron flux over a few minutes is indicative of criticality or:
(
A.
the point of adding hest.
l 5..
supercriticality.
C.
suberiticality.
D, equilibrium subcritical count rate.
QUESTION:
95.
At EOL, critical rod (CTA) position has been calculated for a reactor startup four hours after a trip from 100 percent power equflibrium conditions. The actual critical rod (CEA) position will be lhWER 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 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:
96.
Vith keff - 0.985, how much reactivity must be added to make the reactor
~
critical?
A.
1,480 pcm (1.48% delta k/k)
B.
1,500 pea (1.50% delta.k/k)
C.
1,520 pea (1.52% delta k/k)
D.
1,540 pcm (1.54% delta k/k)
PORN 5 Page 32 of 34
i, ct '
.O o.
PRESSURIEED ilATER REACTOR CENERIC FUNDAMENTA1A EIANIMAT1011 PORN 5 QUESTIO!!:
97.
[
If, during a reactor startup, the startup rate is constant and positive without any further reactivity addition, then the reactor is:
A.
critical.
6 B.
supercritical.
O.
suberitical.
D.
prompt critical.
r QUESTION:
98, l
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 reactivity effect.
C.
The decrease in fuel temperature will begin to create a negative reactivity effect.
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 stable negative SUR is attained. Reactor power vill be reduced to 0.05 percent in approximately seconds.
A.
360 B.
270 C.
180 D.
90 FORM B Page 33 of 34
t 1
t.
0.,
ca -
i FRRSSURIEED WATER REACTOR CDIERIC FUllDMEDf7A1A 32AMINAT1018 PORM B 4'
QUESTION:
100.
l The anjor 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 (CLAs) installed.
C.
an increase in core life.
D.
a reduction in the effect of resonance capture.
j!
r FORM B Page 34 cf 34
'