ML20058E693
| ML20058E693 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/29/1990 |
| From: | Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 9011070275 | |
| Download: ML20058E693 (123) | |
Text
V:
OCi
? :m Docket:
50-445 License: NPF-28 TU Electric ATTN:
W. J. Cahill, Jr.
Executive Vice President -
Nuclear Skyway Tower 400NorthOliveStreet(L.B.81)
Dallas, TX-75201 Gentlemen:
This letter forwards the results of the Generic Fundamentals Examination Section(GFES)ofthewrittenoperatorlicensingexaminationthatwas administered on October 10,.1990, to nominated employees of your 1acility.
We are forwarding the following 1.tems:
o the examinations, including answer keys o
the results for your nominated employees, and o
copies of the individual; answer sheets completed by your nominated employees We request that your training department forward-the individual answer sheets-and results'to the appropriate individuals.
It should be noted that the examination was administered in two forms, which were identical except for tne sequence of questions.
In accordance with the Consission's Regulations,10 CFR Part 2.790, a copy of this letter and the examination and answer key will be placed in the NRC's Public N eument Room (PDR). 'The individual results and answer sheets are exempt from public disclosure 4and therefore will not be placed in the PDR.
Questions concerning this examination should be directed to Mr. Paul Doyle at(301)492-1058.
t Sincerely, w b (d1MN 4 [amuel J. Collins, Director L
p j
S Division of. Reactor Projects y
L
Enclosures:
As stated l-cc:
next-page i'
1 S
9011070275 901029 h
PDR ADOCK 05000445
/
l.;
V PNV g
r.
1
-2 cc:
Texas Utilities Generating Company
. Comanche Peak SES ATTH: Jerry McMahon, Director Nuclear. Training P. O. Box 2300
- Glen Rose, TX 76043 t
i4
,_+i-3 4,1 t
[
DRS:0LS:SC DRS:DivDir DRP:DivDir l
-JLPellet LJCallan SJCollins 10/29/00 10p/90
'10/3/90 i
t l
i
bec to DMB-(IE42) bec distribution by RIV:
R. D. Martin MIS-System-J. L. Pellet E. M. Himes flRR Project Manager (itS: 13-D-18)
DRP SC RIV file i
L. Miller,'TTC DRS (J. Pellet rdg file)
J. Ellis, CASE i
i t
l
..,, p
'. *O l
l l
l
PWR GFE - DCTOBER 1990 - ANSWER KEY (Form A) 35.
B 69.
A 1.
C 3
2.
D 36.
D 70.
A 3.
A 37.
C 71.
B 4.-
B 38.
D 72.
B 5.
D 39.
D 73.
D 6.
C 40.
C 74.
C 7.
D 41.
A 75.
D 8.
C 42.
C 76.
B 9.
C 43.
A 77.
C 10.
B 44.
B 78.
A 11.
A 45.
A 79.
A 12.
C 46.
B 80.
B 13; D
-47.
B 81.
C l
14..
A 48.
B 82.
C 15.
B 49.
A 83.
D 16.
B 50.
C 84.
A 17.
A 51.
D 85.
C 1
- 18. -
A-52.
B 86.
D e
19.
C-53.
B 87.
A 20.
B 54.
A 88.
A 21.
C 55.
D 89.
D 22.
.D 56.
A 90.
A 23.
B 57.
A 91.
D 24.
A 58.
C 92' A
25.
B' 59.
B 93.
D 26.
D 60.
C 94; B
L-27; B
16 1.
C 95.
D 28.
C-62.
D 96..
D-29.
A 63.
A 97.
C 30.
A 64.
B 98.
C r.
31.
D 65.
D 99.
D
- 32. -
A 66.
A 100.. B.
33.
C 67.
B l'
34.
C 68.
A l
o l-l,
PWR-GPi - OCTOBER 1990 - ANSWER KEY (Form B) 1.
D' 35.
D 69.
D 2.
C' 36.
B 70.
A
'3.
D 37.
B 71.
B 4.
B 38.
A-72.
B 5.
C 39.
D 73.
A i
6.-
'A 40.
A 74.
A
-7.
A 41.
A 75.
C 8.
B 42.
C 76.
B
- 9. -
C 43.
B 77.
C 10.
C 44.
C 78.
D-11.
D 45.
C 79.
B 12.
A.-
46.
D 80.
A 13.
C 47.
A 81.
B 14.
D 48.
B 82.
D 15.
A 49.
D 83.
B 16..
A 50.
A 84.
C 17.
D 51.
B 85.
A 18.
A 52.
A 86.
A 19.
D 53.
A 87.
D-20.
A 54.
A 88.
A 21.
D 55.
B 89.
C 22.
B 56.-
B 90'
- C 23.
D-57.
C 91.
8-24.
<D 58.
D 92 '.
D-q 25.
C' 59.
A
- 93.
C.
3 26.
C-60.
B-94.
D' 27.
D-61.
D 95.
D 28.
B 62.
C 96.
C-29.
A 63.
D 97.
A i
30.-
B 64.
C 98.
C
-I
! 31~. -
B 65.
C 99.
A 32.
B
- 66. '
B 100.
B 33.
A 67.
A 1
34.
C-68.
C i
u
PWR Exam
=
Corrections Instructions: Have candidates make these changes prior to starting the clock for the-Examination.
Question: 16(72)
Change to read:
Which type of radiation detector is the most sensitive to low >1evel gama radiation.
Question: 18 (74)
Pen and Ink:
Change " air pressure" in choices A and B to " control air pressure".
Question:
39 (95)
Pen and. Ink Add.th'e following sentence:
The breaker is normally open.-
Question:-
79 -( 7)
Clarification.
With respect to normal operations.
- a t
r
\\
ee UNITED STATES NUCLEAR REGULATORY COMMISSION PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1990 - FORM A P
Please Print:
Name:
. Facility:
ID Number:
l l
l_
Start Time:
Stop Time:
1:
INSTRUCTIONS TO CANDIDATE
_Use the answer-sheet provided.
Each question has equal point p
value.- A score of at least 80% is required to-pass this portion of the written licensing examination.~
All examination papers will:be collected 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'
% OF TOTAL SCORE COMPONENTS, 1 - 44 REACTOR. THEORY 45 - 72 THERMODYNAMICS 73 100 TOTALS'
'100 All. work done on this examination is my own.
I have-neither given-nor received aid.
Candidate's-Signature FORM A
r INSTRUCTIONS FOR FILLING OUT THE ANSWER SHEET FOR THE OCTOBER 10, 1990 GENERIC FUNDAMENTALS EXAMINATION STUDENT ENROLLMENT SIDE BLANK / TITLE WHAT YOU SHOULD FILL IN INSTRUCTOR Write in the name of the nuclear plant you are presently associated with.
CLASS Write in the type of facility sponsored training program you are currently enrolled in (e.g. R0, SRO Upgrade, SRO Instant,etc.) Do @I include requalification programs.
STUDENT 1.D.
A five digit number. This number is supplied by the NUMBER proctor.
If you don't know ask the proctor.
AREA CODE Enter the last three numbers of your facility's "50" docket number.
(Write in the boxes and darken the corresponding spaces.)
t PHONE NUMBER LEAVE BLANK LAST NAME/
Enter your last name, followed by a space, your first name, FIRST NAME/
leave a space then your first initial.
(Write in the boxes M.I.
and darken the corresponding spaces.
CODE Enter the two letter core which applies to you from the i
table below.
CATEGORY CODE Formerly NRC-Licensed Personnel:
FORMER LICENSE-LICENSE CLASS Reactor Operator Reactor Operator RT Senior Reactor Operator Senior Reactor Operator ST Reactor Operator
. Senior Reactor Operator RA NEVER NRC Licensed Personnel:
LICENSE CLASS Reactor Operator.
UR Senior Reactor Operator US 9
TEST ANSWER SIDE Bj.Mg/ TITLE WHAT YOU SHOULD FILL IN
-ID NUMBER Write your ID number (the same one you filled out'on the other side.
TEST FORM Fill in the appropriate space. All tests are designated.
either A or B form on the cover sheet.
EXAM FORM Fill in the 0,0,0 spaces.
l l
5
t RULES AND GUIDELINES FOR THE g
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 your facility.
(3)
Fill in the ID-Number you were given at registration.
(4)
Fill'in your start and stop times at the appropriate time.
(5)
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.
(6)
Use only the answer sheet provided.
Credit will only be given for answers _ properly marked on this sheet.
Follow the instructions for filling out the answer sheet.
(7)
Scrap paper _will be provided for calculations.
(8)
Any questions about.an item on the examination should be directed to the examiner only.
(9)
Cheating on the examination will result in_the automatic forfeiture of this examination._ Cheating could also result in severe penalties.
-(10)1Restroom trips are limited. Only ONE examinee may leave the room at-altime.
In order to avoid'the appearance or possibility of cheating, avoid all contact with anyone outside of-the examination room.
(11) After you have completed the examination, s'ign the statement on the cover' sheet indicating that the work is your own and you-have not received or been given any assiatence in completing the examination.
(12) 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.
(13) After turning in your examination saterials, 1 rave the s
examination area, as defined by the sxaminer.
If after
~
leaving you are found in the examination area while the examination is -in progress, your examinatlein may be forfeited.
FORM'A 4
CENERIC FUNDAMETA13 EXAMINATION SECTION EQUATIONS AND CONVERSIONS HANDOUT SHEET EOUATIONS 6
Ee AT-Cycle Efficiency = Net Work (out)
P Energy (in) 4 5 Ah SCR S/(1. K,gg)
=
6 UA AT cry (1. K,gg)
=
CR II
- Keff)2
=
2 SUR = 26.06/r M
1/(1 K,gg)
CR /CR y
0 26.06 (1,gg p)
(1. geff)0 SUR g
,,(# * #)
(1 K,gg)y SUR(t)
P P, 10 seg
=
(1. geff)fgeff P, e(t/r)
P
=
Pwr V a g
(1*/p) + ((g-. p)/A p) r 1*f(p, g) r (K,gg. 1)/K,gg 1*
1 x 1o.5 seconds p
=
AK,gg/K,gg A,gg = 0.1 seconds'1
~
3(P, - P ) i f (7,2 _ y 2) + g( r, - z ) -
0 g
g CONVERSIONS 10 1: Curie 3.7 x 10 dps.
1 kg 2.21 lba 1 hp -
6 2.54.x 10 BTU /hr 1 Mw 3.41 x 10 BTU /hr
'l BTU-778 ft lbf
'F
=
9/5 *C + 32
=
- C 5/9 (*F. 32)
=
,_a, a.~.
n.---
.a 2 +
.+.m s.-
n
.s m----o-as a-
. ur
.aa w..<.-a.a na
_as a me - a s ~s~,-anx...,_s,_,.n_,
h 9
/
i S
2 AIR SUPPLY VENT r
s t
2 a
f i
SPRING-LOADED AIR-OPERATED VALVE I
FIGURE 1 i
REFERENCE LEG FILL CONNECTION 6
GAS OR VAPOR PRESSURE h
.((,
L WATER /
EQUALIZING l
VALVE m
D/P
. DETECTOR 1.
TANK DIFFERENTIAL PRESSURE LEVEL DETECTOR.
FIGURE 2
PRESSURIZER CONDENSING POT
, STEAM
_ l l
EQUALl21NG VALVE WATER h
l f//)
D/P DETECTOR j
PRESSURIZER DIFFERENTIAL' PRESSURE LEVEL DETECTOR FIGUP5 3 l
l
\\
(;
l
,' STEAM CONDENSING POT
/
/
/
hA NG TER E r
,/
=
L~f M
D/P 7----
DETECTOR I
I I
I STEAM GENERATOR DIFFERENTIAL PRESSURE LEVEL DETECTOR l
FIGURE 4
IIP CONVERTER FROM p
SGWLC.
F LOGIC LOGIC-d -
L-VALVE POSITIONER q
g emem Af
-4 8-eewees 3
ATMOSPHERE :
3 aL
)
AIR SUPPLY FROM
\\ [
TO I
h FEED S T E A T.1 AIR SUPPLY PUMPS FEED GENERATOR CONTROL AIR emmesme CONTROL VALVE LOGIC SIGNAL ----
PNEUMATIC CONTROL SYSTEM FIGURE 5
SPRING p FLYBALL FULCRUM g
,b N 2
FUEL ON FUEL OF FULCRUM 6
8 FUEL PIPE FLYBALL WElGHT MECHANICAL SPEED GOVERNOR FIGURE 6
.-a.eaa&
4 4
^-^
HEAT EXCHANGER l
' O PUMP l
COOLING WATER SYSTEM FIGURE 7
J i
^
w 4
HEAT EXCHANGER V' O PUMP A
\\
M O PUMP B COOLING WATER SYSTEM FIGURE 8 l
l
(
I t
= :_ _
LP FLUID TANK 90'F v
1
/
120cF FAILED TUBE i
HP FLUID c..
0 PUMP l
COOLING WATER SYSTEM FIGURE 9
t l
l s
CLAD l m rw_
J l
I FUEL PELLET I
w n
.3 R
I j '.
F 7
lJ w_
l I
l l
n o
W t J i
l m ew J
l l
l COOLANT l
COOLANT FLOW
% _i J FLOW s
/$ l Av.
l
[
FUEL ROD AND COOLANT FLOW CHANNEL l
FIGURE 10 1
l
. ~ _ -
m CLAD r
m e
s I
ga~
FUEL PELLET w
,s s.,.
g F l3 l
l W
J
~
I s<.
l o
o w,,
i 1
F w. >
l I
A l
COOLANT l
COOLANT FLOW j'
u is FLOW l
x l
FUEL ROD AND COOLANT FLOW CHANNEL FIGURE 11
1
' QUESTION:
1 Refer to the drawing of a spring-loaded air-operated valve (see figure 1).
Upon a loss of air pressure, this valve will A.
go to the fully open position.
B.
remain at the current position.
C.
go to the fully closed position.
D.
go to the mid-position.
QUESTION:
2 operators should use BOTH hands on valve handwheels when positionin,J LARGE manual valves tot A.
overcome the resistance of installed locking devices.
B.
control the rate of valve motion to prevent water hammer.
c.
ensure system pressure, temperature, and flow are controlled during valve motion.
D.
control lateral force to prevent bending the valve stem.
1 l
QUESTION:
3 i
When manually positioning a motor-operated-valve, care must be taken to avoid using excessive valve seating /backseating l
force because:
l A.
the valve might not operate on demand.
B.
torque switch settings may change.
c.
limit switch settings may change.
e D.
the valve motor will not reengage.
l FORM A 3
i
- QUESTION:
4 To verify a manual valve in an operating system is closed, the operator should operate the valve handwheel in ther A.
open direction until the valve is fully open, then reclose 4.t using normal force.
B.
close direction using normal force and verify there is no substantial handwheel movement.
C.
open direction until flow sounds are heard, then reclose the valve using normal force.
D.
close direction until it stops, then close it an additional one-half turn using additional force if necessary.
QUESTION:
5 When comparing the characteristics of gate and globe valves in an operating system, a globe valve generally has the pressure drop when fully open and is the better valve for flow.
A.
lower; isolating B.
higher; isolating C.
lower; throttling D.
higher; throttling l
FORM A 4
... ~
' QUESTION:
6.
(
The density compensating input to a steam flow instrument is used to convert volumetric flow rate to l
A.
velocity flow rate.
i B.
gallons per minute.
C.
mass flow rate.
D.
differential flow rate.
QUESTION:
7 If the liquid flowing through a differential pressure liquid flow rate detector contains entrained voids (gas or steam), indicated flow rate will be A.
erroneously high.
B.
erroneously low.
C.
unaffected.
l D.
fluctuating.
i t
I
(
QUESTION:
8 l
Which of the following will cause indicated volumetric flow rate to be LOWER than actual volumetric flow rate using a differential pressure (D/P) flow detector and a calibrated orifice?
A.
Debris becomes lodged in the orifice.
B.
A leak develops in the low pressure sensing line.
C.
The orifice erodes over time.
l D.
System pressure decreases.
1 FORM A 5
QUESTION:
9 Flow detectors (such as an orifice, flow nozzle, and venturi tube} measure flow rate using the principle that flow rate ist
~
A.
DIRECTLY proportional to the differential pressure squared.
B.
INVERSELY proportional to the differential pressure squared.
C.
DIRECTLY proportional to the square root of the differential pressure.
L D.
INVERSELY proportional to the square root of the differential pressure.
L QUESTION:
10 Refer to the drawing of a tank differential pres.ure level detector (see figure 2).
If the differential pressure detector equalizing valve is opened, level indication will:
A.
decrease and stabilize below actual level.
E B.
increase and stabilize above actual level.
C.
oscillate above and below actual level.
D.
remain constant r.t the current level.
r F
FORM A 6
m
' QUESTION:
11 Refer to the drawing of a pressurizer differential pressure level detector (see figure 3).
With the plant at normal operating conditions, a pressurizer level dif ferential pressure (D/P) instrument, that had been calibrated while the plant was in a cold condition, would indicate than actual level because of a differential pressure sensed by the D/P detector at normal operating conditions.
A.
lower; larger B.
lower; smaller C.
higher; larger D.
higher; smaller QUESTION:
12 Refer to the drawing of a steam generator differential pressure level detector (sce figure 4).
Which one of the following failures will cause the associated steam generator level indicator to indicate the LOWEST level?
A.
The D/P detector diaphragm ruptures.
B.
The reference leg ruptures.
C.
The variable log ruptures.
D.
The equalizing valve is opened.
FORM A 1
l t
- QUESTION:
13 If the pressure sensed by a bourdon tube increases, the curvature of the detector will because of the greatest force beina applied to the curve of the detector.
A.
increase; inner B.
decreaser inner C.
increase; outer D.
decrease; outer QUESTION:
14 If a rc*istance temperature detector (RTD) develops an OPEN circuit (bridge circuit remains intact), indication will fail:
A.
high.
B.
low.
C.
as is.
D.
to mid-scale.
FORM A 8
i
i QUESTION:
15 The plant has experienced a loss of coolant accident (LOCA) With degraded safety injection flow.
The reactor coolant pumps (RCPs) have been manually tripped and the resulting phase separation caused the upper portion of the core to uncover (approximately 20 percent).
Which one of the following describes excore source /startup range neutron level indication following the cora uncovering, relative to the indication just prior to the core uncovering?
A.
Significantly less B.
Significantly greater C.
Essentially unchanged D.
Impossible to estimate with the given core conditions.
QUESTION:
16 Which type of radiction detector is generally used to perform a survey in e LOW level gamma radiation area?
A.
Ion chamber B.
Proportional D.
Scintillation FORM A 9
QUESTION:
1,7 i
If the turbine shaft speed signal received by a typical turbine governor control system fails low during turbine startup, the turbine governor will cause turbine speed to:
A.
increase, until an upper limit is reached or the turbine trips on overspeed.
B.
decrease, until the mismatch with demanded turbine speed is nulled.
C.
decrease to minimum speed.
D.
cycle approximately 5 percent above and below the current speed.
QUESTION:
18 Refer to the drawing of a pneumatic control system (see figure 5).
The purpose of the valve positioner is to convert:
A.
a small air pressure into a proportionally larger air pressure to adjust valve position.
B.
a large air pressure into a proportionally smaller air pressure to adjust valve position.
l C.
pneumatic force into mechanical force to adjust valve position.
D.
mechanical force into pneumatic force to adjust valve position.
l l
l l
l FORM A 10
'T*
w w
.--a.-
w.ese-
~
a
QUESTION:
19 Refer to the drawing of a flyball-weight mechanical speed governor (see figure 6).
In a flyball-weight mechanical speed governor, the purpose of the spring on the flyball mechanism is to:
A.
counteract centrifugal force by driving the flyballs apart.
B.
aid centrifugal force by pulling the flyballs together.
C.
counteract centrifugal force by pulling the flyballs together.
D.
aid centrifugal force by driving the flyballs apart.
QUESTION:
20 What precaution must.be observed when transferring a valve controller from the automatic mode to the 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 l
matched between automatic mode and manual mode.
C.
Ensure that the automatic valve controller signal is decreasing before transferring to the manual mode of Control.
D.
Ensure that the. automatic valve controller signal is increasing before transferring to manual mode of l
control.
1 FORM A 11
QUESTION:
21 i
Pump cavitation occurs when vapor bubbles are formed at the eye j
of a pump impeller:
A.
when the localized flow velocity exceeds sonic velocity for the existing fluid temperature.
B.
when the localized pressure exceeds the vapor pressure for the existing fluid temperature.
' c.
and enter a high pressure region of the pump where they l
collapse causing damaging pressure pulsations.
D.
and are discharged from the pump where they collapse in downstream piping causing damaging pressure pulsations.
r QUESTION:
22 The presence.of air in a pump casing _may result in when the pump is started.
A.
Lvortexing
- B.
pump runout c.
pump overspeed D.
gas binding 4
FORM A 12 m
.m.
.s._.
., -.....-,,., m
.... ~.
~..
- QUESTION:
23 operating a motor-driven centrifugal pump for an extended period of time under no flow conditions will causet A.
pump failure from overspeed.
B.
pump failure from overheating.
C.
motor failure from overspeed.
D.
motor failure from overheating.
QUESTION:
24 Refer to the drawing of a cooling water system (see figure 7).
The centrifugal pump is circulating water at 100 degrees F.
Af ter several hours the water temperature has increased to 200 l
degrees F.
Assuming system flow rate.(gpm) is constant, pump motor amps will have because A.
decreased; water density has decreased B.
increased; water density has decreased C.
decreased; pump shaft speed has increased D.
increased; pump shaft speed has increased i
l l
1' s
FORM A 13 w
,.,-,-..-,-,,n,.
,. - +.,.---., -..,, -
-e
-.,e.-,nm,-,
k QUESTION:
25 Refer to the drawing of a cooling water system (see figure 8) in which pumps A and B are identical single-speed centrifugal pumps.
Compared to system operating. conditions with only pump A operating, after pump B is started, system flow rate will be approximately and pump discharge pressure will be approximately A.
constant; double B.
doubler constant C.
constant; constant D.
double; double QUESTION:
26 If the speed.of a positive displacement pump is increased, the available not positive suction head (NpSH) will and the probability of cavitation will r
A.
decrease;'not change L
B.
not. change; decrease 1
l C.
increase; decrease L
D..
decrease; increase I
5 FORM A 14
~.
QUESTION '
27 i
An operator can dif ferentiate a locked reactor coolant pump (RCP) rotor from a sheated RCP rotor 30 seconds after the event by the:
(Assume no operator action.)
A.
loop flow indications.
B.
RCP ammeter indications.
C.
loop differential temperature indications.
D.
reactor trip status.
QUESTION:
28 A centrifugal pump is operating at 600 rpm with the following parameters:
Current = 10 amperes Pump Head = 50 psi Pump Flow Rata = 200 gpm What will be-the new value of pump head if the flow is increased such that the current requirements are now 640 amperes?
A.
400 psi B.
600 psi C.
800 psi D.
1,200 psi FORM A 15
i l
QUESTION:
29 If the discharge valve of a large AC motor-driven centrifugal pump remains closed during a normal pump start, the motor ammeter l
indir,ation will rise to:
1 A.
several times the full-load current value and then decrease to the no-load current value.
B.
approximately the full-load current value and then decrease to the no-load current value.
C.
several times the full-load current value and then decrease to the full-load value.
D.
approximately the full-load current value and then stabilize at the full-load current value.
QUESTION:
30 The number of starts for an electric motor in a given period of time should be limited because:
A.
overheating of the-windir.ge can occur due to high starting currents.
I B.
rotor damage can occur due to excessive cyclic stresses on the shaft.
L C.
overheating of the windings can occur due to shorting within the stator.
rotor damage can occur due to excessive axial displacement of
(
D.
the shaft.
l FORM A 16
I QUESTION:
31 A main generator is operating on the grid with the following indications
- 100 MWe
- 0 MVAR
- 2,800 amps
- 20,000 volts If main generator excitation is reduced, amps will and NWe will A.
decrease; decrease B.
increase; decrease c.
decrease; remain the same D.
increase; remain the same QUESTION:
32 Whenever possible, a heat exchanger should be placed in service by introducing both fluids gradually and simultaneously to:
A.
prevent excessive thermal stresses in the heat exchanger.
B.
maximize the heat transferred across the heat exchanger tubes.
c.
minimize boiling of the cooling water in the heat exchanger tubes.
D.
provide maximum temperature control of the system being cooled.
t i
FORM A 17
I 1
QUESTION:
33 Tube scaling in a parallel-flow heat exchanger will cause heat transfer to decrease because:
i A.
flow through the heat exchanger increases.
B.
surface area of the tubes decreases.
C.
heat transfer coefficient decreases.
D.
inlet temperature of the cooling fluid increases.
r QUESTION:
34 Refer to the drawing of an operating cooling water system (see figure 9).
Which of the following effects would occur as a result of a tube FAILURE in the heat exchanger?
t A.
High pressure fluid flow rate decreases.
B.
Flow in the low pressure system reverses.
C.
Temperature in the low pressure system increases.
c.
i D.
Level in the~ tank increases.
l' QUESTION:
35
.The purpose of a domineralizer is to:
l i
A.
raise the conductivity of water without affecting pH.
B.
reduce the conductivity of water without affecting pH.
C.
increase the pH of water by reducing the number of positively charged ions in it.
D.
decrease the pH of water by increasing the number of negatively charged ions in it.
FORM A 18
, ~ _
~
' QUESTION:
36 Prior to a scheduled plant shutdown, the reactor (primary) coolant system was chemically shocked to induce a crud burst.
What effect will this have on the letdown purification domineralizers?
A.
Increased flow rate through the domineralizers B.
Domineralizers will become boron saturated C.
Decreased dominera'lizer outlet conductivity D.
Increased pressure drcp across the domineralizers QUESTION:
37 A domineralizer is BORON SATURATED when the domineralizer A.
effluent contains a higher boron concentration than the domineralizer influent.
B.
absorbs greater than 20 ppm boron per hour.
C.
influer,t and effluent boron concentrations are equal.
l D.
eft:.uent boron concentration rapidly increases.
QUESTION:
38 To doenergize a component and its associated control and indication circuits, the component circuit breaker should be:
A.
open with control power fuses removed.
l B.
racked in with control power fuses removed.
C.
racked out and tagged in racked-out position.
D.
racked out-with control power fuses removed.
FORM A 19
QUESTION:
39 The following remote indications are observed for a 480 VAC load supply breaker.
Red indicating light is on.
Green indicating light is off.
Load voltage indicates 0 volts.
Line voltage indicates 480 volts.
What is the condition of the breaker?
A.
Open and racked in B.
Closed and racked in C.
Open and racked to " test" position D.
Closed and racked to " test" position l
QUESTION:
40 Loss of breaker control power will:
A.
remove all local indication of breaker position.
t l
B.
prevent local tripping of the breaker.
l C.
remove the breaker tripping function on remote interlock.
D.
prevent the breaker from tripping on overcurrent.
i FORM A 20
- -,. _,.. _ _ _,. _ _ _ _ _.. _.. _ ~
i
?
QUESTION:
41 During paralleling operations of the main generator to the grid, closing the generator output breaker with the frequency of the generator at 60.1 hertz and the grid frequency at 60.0 hertz willt j
A.
cause the generator to immediately increase load.
B.
trip open the generator breaker on reverse power.
C.
cause the generator voltage to increase.
D.
cause the generator current to decrease.
QUESTION:
42 Which of the following describes the BEST method for completely deenergizing a breaker control circuit?
A.
Breaker in test position.
B.
Breaker fully racked out.
C.
Control power-fuses removed.
D.
Control switch in pull-to-lock.
' QUESTION:
43 The function of high voltage electrical disconnects is to provide r
electrical isolation of_ equipment during conditions.
A.
' manual; no-load B.-
manual; overload-C.-
automatic; no-load D.
automatic; overload FORM A 21 j
c l
l
b
' QUESTION:
44 i
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 cubjected 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.
1 L
i
- 1. c l,
,s i
l(
t ( _~
FORM A 22 o-If
- 1. i
i QUESTION:
45 Which of the following conditions describes a reactor that is EXACTLY critical?
A.
X,,, = 1; delta-K/K = 0 B.
K,, e 1; delta-K/K = 1 C.-
K.,, = 0 ; delta-K/K = 0 D.
K.,, = 0 ; delta-K/K = 1 QUESTIOl;:
46 With K,, = 0.987, how much reactivity must be added to make the reactor exactly critical?
A.
1.30% delta-K/K
=B.
1.32% delta-K/K.-
. C.-
1.34%. delta-K/K
. 1.36% delta-K/K D.
}
b
}.
FORM A 23 t
2
QUESTION:
47 A reactor is operating at steady-state 90 percent power with all control rods-(CEAs) fully withdrawn and T at 580 degrees F.
A reactor-trip occurs, after which T stEEilizes at 550 degrees F and all-rods (CEAs)are verifieI*to'be fully inserted.
Given!the following information, calculate the value o'
Assume no operator actions and disregard any reactivity effects of xenon.
Power Coefficient = -0.01% delta-K/K/% power Control / Regulating Rod Worth = -2.788% delta-K/K Shutdown / Safety Roo Worth = -4.130% delta-K/K MTC = -0.01% delta-K/K per degree F r
-5.718% delta-K/K s
B.
-6.018% delta-K/K C.
-i.518% delta-K/K D.'
-7.818% delta-K/K 4
QUESTION:
48 LA subcritical reactor.has an initial source /startup range count rate ofi l50 cps with a shutdown reactivity of -2.0% delta-K/K.
How much positive reactivity must be added tofestablish a stable
' count rate of-300 cps?
O
- - A. ; 0.5%> delta-K/K B.
1.0% delta-K/K C.
.l1. 5% ! delta-K/K
'D.
2.0% delta-K/K 10 -,a FORM A 24 4
d 3
i-i-
0
' QUESTION!
49 L
t
-Which one of the following conditions will initially result L
l-in a positive startup rate when the reactor is at power?
'A.
Increase in turbine loading B.
Unintentional boration
'C.
Turbine runback D.
Accidental closure of a main steam isolation valve QUESTION:
50 4
Moderator temperature coefficient will be LEAST NEGATIVE at a reactor coolant temperature and a
- reactor, coolant boron: concentration.
'A.
low;' low' i
B.
hight low C.
. low; high J
K
.D.
high; high.
l' li J
-QUESTION:
51 l
l
~The amount of-boric acid required to' increase.the coolant L
-boron; concentration by 50 ppm at BOL conditions (1200 ppm) is p
approximately as the amount'of boric acid required.to increase boron concentration by 50 ppm at EOL'(100 ppm).
-s A.
twelve times as large B.
eight cimes as large C.
four times' as large:
D.
the same-FORM A 25 i
1 l
l.
QUESTION.
52
.The plant is being returned to operation following a refueling outage.
Fuel preconditioning requires reactor power being increased from 10 percent to full power gradually over a ONE WEEK period.
During this slow power increase, most of the positive reactivity j
added by the operator is required to overcome the negative reactivity from l
A.
fuel burnup.
B.
xenon. buildup.
C.
fuel ^ temperature increase.
D.
moderator temperature increase.
.b
- QUESTION:
53.
Which one of the'following statementsLconcerning the power defect is correct?
The power defect necessitates the use of a ramped T,, ling program A.
to maintain an adequate Reactor Coolant System subcoo I
margin.
-i B.
The power defect increases theirod (CEA) height requirements i
necessary to maintain the desired shutdown margin following a l
l' reactor trip.
e u
+
l C.
The power defect is more negative at the'beginning of core life-because of the higher. boron concentration.-
1
.D.
The power' defect causes control rods (CEAs).to be withdrawn as reactor power is decreased.
j
- i FORM A 26 l
l QUESTION:
54 Differential rod worth will be the greatest if RCS temperature is and RCS boron concentration is
. A.
increased; dai:reased B.,
decreased; decrtased C.
increased; increased D.
' decreased; increased QUESTION:
55 Which'one of the following describes why most of the power is.
)
produced;in the lower' half of a core that has been operating at I
100 percent power for several weeks at the beginning of core-life?
A.
Xenon concentration is lower in the: lower half of the Core.
i B.
The moderator to-fuel. ratio is lower in the lower half of the Core.
I E
.C.
- Thel fuel 11oading in the lower _ half of the core-contains a higher U-235 enrichment.
- D.,.Theimoderator temperature coefficient of reactivity is-adding less negative-reactivity in the: lower half of the core'.
w i
L 1
FORM A 27-l:L i J--
i
1
' QUESTION:
56 l
The basis for the maximum power density (kw/ft) power limit is to:
A.
provide assurance of fuel integrity.
B.
prevent xenon oscillations.
C.
allow for fuel pellet manufacturing tolerances.
l D.
prevent nucleate boiling.
l QUESTION:
57 J
The plant is operating at equilibrium 30 percent power level at EOL with.all control rods'(CEAs) fully withdrawn.
If control D
rods (CEAs) are partially INSERTED,.the axial neutron flux will-shift from-the of the reactor core.
.A.
top to'the. middle B.-.
middle to the bottom i
l;i-C.
. middle to the top D.
' bottom to the middle-a
.i QUESTION:
58
- Twoicharacteristics of Xe-135 that result in.it'being L MAJOR 4
reactor. poison are its relatively) half-life and i
relatively absorption cross section.
1 l.
A.
.short; large.
i -
1B.
short; small
~
l L ~"
C.
long;: large.
}
D..
long; small FORM A 28 I
i
...- -.-m r
' QUESTION:
59 Two: identical: reactors have been operating at a constant power level for one week.
Reactor A is at 50 percent power and Reactor B is at 100 percent power.
If both reactors trip / scram at the same time, xenon-135 will peak first in reactor and the L
highest xenon-135 reactivity peak will occur in reactor A.
Al A
' B.
A; B s
C.
B; A D.
B; B l
L i
QUESTION:
60 Reactor power is increased from 50 percent to 60 percent in one L
hour.- The most-significant contributor to the initial change in xenon reactivity is the increase in:
~ A.
xenon production from fission.
i.
B.
'cf -xenon absorption of neutrons.
D..
' xenon production from iodine decay.
- L' s
i 1
!;- T s
FN
~
4 FORM A 29 l<
o
- -. - - - - = -
\\
' QUESTION:
61 1
-A reactor has been operating-at 50 percent power for a week when power is quickly ramped (over 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)-to 100 percent.
How will the xenon concentration in the core respond?
.A.
Decreases initially, then builds to a new equilibrium concentration in 8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
B.
Increases steadily to a'new equilibrium concentration in 20 to 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
C.
Decreases initially, then builds to a new equilibrium concentration in 40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
D.
Increases steadily to a new equilibrium concentration in 60 to-70 hours.
l:.
L
- QUESTION
62 1
A reactor that has.been operating at rated power for about two
- weeks reduces power to 50 percent.
Xenon-135 will reach a new equilibrium condition in-hours.
A..
8.to 10:
L; l
~B.
'20 t'o 25-C..
'30 to 35 l
D.
40.to:50 i.
l' l-l
~
FORM A 30 r
1 I
l
' QUESTION:
63 1
A-reactor has been operating at 100 percent power for several weeks with power production evenly distributed axially above and below the core midplane.
Reactor power is reduced to 50 percent using boration to control T,, while maintaining control rods (CEAs) fully withdrawn.
The axial power distribution will:
A.
shift toward the top of the core.
B.
shift toward the bottom of the core.
C.
, remain evenly distributed above and below the core midplane.
D.
peak at the top and the bottom of the core.
l QUESTION:
'64 During a six-month period of continuous full' power reactor operation, the RCS boron concentration must be decreased steadily to compensate for:
A.
buildupLof fission product poisons and burnable poison burnout.
- I B.
'fuelfdeplation and buildup of fission product poisons.
-C.
decreasing control rod.(CEA) worth and burnable poison
-burnout.
D.
burnable poison burnout and fuel depletion.
i FORM A 31
,....,r s
. - ~.,,
,.7
d QUESTION:
65 While withdrawing _ control rods-(CEAs) during an approach to criticality, the stable count rate doubles.
If the same amount of reactivity that caused the first doubling is added again, stable count rate will and the reactor will be E
A.
increase but not double; suocritical B.
double; subcritical i.
l C.-
double; critical l
D.
- more than double; critical l
l l-t l
1:
-l QUESTION:
66' 1
L During a reactor-startup, as X,,, increases toward criticality, l
- the value of~1/M:
A.
~ decreases toward zero.
B.-
decreases toward one.
C.
increases toward infinity.
D.
. increases toward one.
1 l
l l
l:
l i
FORM A 32
-28 m
e-m y
y
I
'QUESTION:
67 i
An. estimated critical rod position (ECP) has been calculated for a reactor startup that is to be performed 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a trip from a 60 day full power run.
Which one of the following events or conditions will result in the actual critical rod position being LOWER than the ECP?
A.
The.startup is delayed for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
B.
The main steam header pressures are decreased by 100 psi just prior to criticality.
C.-
A new boron sample shows a current boron concentration 20 ppm higher than that used in the ECP calculation.
D.
Steam generator feedwater addition rate is reduced by 5 percent ~just prior to criticality.
QUESTION:
68
-Which of the following, if changed, will have the MOST SIGNIFICANT effect on-reactivity while the: reactor is critical below the point of adding heat?
A.-
Coolant temperature and rod (CEA). position-l B '.
Coolant ~ temperature and coolant pressure C.
-Rod (CEA). position and~ reactor. power D.
Coolant! pressure and reactor = power L
L o
l I.
FORM A-33 L
4
.~
ll
\\
s QUESTION:
69 A teactor is subcritical by 1.0% delta-K/K.
The operatur dilutes the RCS by 30 ppm boron.
Assuming boron worth is 0.02',% delta-K/K per ppm and that no other reactivity changes occur, t).e reactor l
1s:
A.
suberitical.
B.-
critical.
C.
supercritical.
D.
prompt' critical.
' QUESTION:
70-
- 7. reactor startup is being performed following a one-month shutdown period.
If the reactor is taken critical and then stabilized at 10,000 cps in the source /startup range, over the l
next 10 minutes the count rate will:
L i
A.-
remain constant.
l B.
decrease linearly.
C.
decrease geometrically.
D.
decrease exponentially.
QUESTION:-
71 A reactor is operating just above the point'of adding heat.
In order to raise reactor power.to a higher stable power level, the operator'must. increase:
}
.A.. steam generator levels.
B.
steam demand.
C.
T,..
D.
reactor coolant system boron concentration.
FORM A 34 i
4
' QUESTION:
7.2 The magnitude of decay heat generation is determined primarily by:
A.
core'burnup.
B.
power history.
c.
final power at shutdown.
D.
control rod worth at shutdown.
FORM A 35
1
]
QUESTION:
73 LAssumingfan atmospheric pressure of 15 psia, 5 inches of Mercury (Hg) vacuum is equivalent tos l
A.
2.5 psia.
B.:
5.0 psia.-
C.
10.0 psia.
D.
12.5 psia.
1 QUESTION:.
74 If condensate teraperature in the hotwell is 6 degrees F subcooled with a temperature of 112 degrees F, what is the condenser pressure?
A.
1.1 psia i
'B.
1.4 psiaL C.
1.6 psia L
l L
D..
1.9 psia i
(...
QUESTION:
75 oCondensate depression is the process of:
a A... removing condensate from turbine exhaust' steam.
B.
! spraying condensate-into turbine exhaustLsteam.
-C.
heating turbine exhaust steam above its saturation i
s-temperature.n D..-
cooling turbine-exhaust; steam'below its saturation temperature.
FORM A 36 l
l
' QUESTION:
76
-The plant is maintained at 2,000 psia with a pressurizer temperature of 636 degrees 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 relief valve?
A.
280 degrees-F B.
240 degrees F-C.
190 degrees F D.
170 degrees F QUESTION:
77 condenser pressure is 1.0 psia.
During the cooling process in the condenser the LP turbine exhaust temperature decreases to 101.0 degrees F, at-which time it is a:
A.
saturated liquid.
B._
saturated-vapor.
C.
.subcooled' liquid.
D.. superheated vapor.
QUESTION:
78 To' achieve maximum efficiency, feedwater should enter the steam
> generator and the temperature difference across the tubesLshould be as as possible.
A.
closeLto saturation; small J.
B.,
close to saturation; great C..
as=subcooled as practical; small
'D.
as subcooled as practical; great FORM A 37
~_
~ - -..
s t
DUESTION:
79 A'contrifugal pump is being returned to service after maintenance.
The operator FAILS to vent the pump properly.
When the pump is started the operator should see capacity and discharge head.
A.
lower; lower B.
lower; higher C.
higher; lowar D.
higher; higher
. QUESTION:
80 TheLmajor concern.with starting a feedwater pump with downstream fluid in a saturated condition is:
A.
-cavitation.-
B.
C.
thermal shock, i:
D.-
positive reactivity addition, l
.r
-QUESTION:
81-While on-surveillance rounds, an operator notices that a centrifugal. pump is making a great deal of noise'(like marbles rattling-inside the pump casing) and the discharge pressure is fluctuating.
- This set of conditions indicates:
L A.;, excessive pump discharge pressure.
t
,B.
pump runout.
C.
pump cavitation.
l L
D.-
FORM A 38
QUESTION:
82 Flow instruments used to measure the mass flow rate of saturated
. steam are density compensated because,_for a steam pressure increase at a constant volumetric flow rate, steam density will and the actual mass flow rate will A.
decrease; increase B.
increase; decrease C.
increase; increase i
D.
decrease; decrease l
QUESTION:
83 To-decrease the flow-rate through an operating positive n
L displacement pump, an operator should:
L
' throttle the pump discharge valve.
A.
B.
throttle the pump suction valve.
L l
C.-
decrease-the pump NPSH.
I D.
decrease the pump speed.1 i
- QUESTION:
84 L
Excessive amounts of entrained gases passing thrcugh a single-phase,.(liquid) heat' exchanger is. undesirable because:
. A..
flow' bloc.kage'canioccur in'the heat' exchanger.-
i l
t
' B..
the laminar' layer will increase in the heat exchanger.
. C.
the huat transfer' coefficient will increase in the heat exchanger.
q D.
the temperature difference across the tubes will decrease through the heat exchanger.
FORM A 39 n
sf 1
--.. ~ _. - -
QUESTION:
86 t.
The reactor is operating with the following parameters:
Reactor power - 100 percent Core delta-T 42 degrees F RCS flow rate ~- 100 percent Average coolant temperature
.587 degrees F A station blackout occurs and natural circulation is established with the following stable parameters:
i Decay haat - 2 percent
~
Core delta-T - 28 degrees F Average coolant temperature - 572 degrees F What is the core mass flow rate in percent?
A.
2.0 percent B.
2.5 percent C..
3.0 percent l~
D.-
4.0 percent r
~
' QUESTION : :
86 i
As' heat is' transferred to. water adjacent to a heating. surface,.
b many-factors influence steam bubble formation.
Select the characteristic below that will ENHANCE steam bubble formation.
p A.-
Chemicals dissolved in the water..
m
- B.
The absence of. ionizing radiation exposure to the water.
I C.
.A highly polished heat-transfer surface with minimal l
scratches or cavities.
t l<
D.
The presence of gases dissolved-in the water.
.o
\\
FORM A 40
\\
QUESTION:
87 Nucleate boiling enhances the convective heat transfer coefficient by the thermal conductivity of the coolant and the laminar layer thickness, l
A.
increasing; decreasing B.
increasing; increasing C.
decreasing; decreasing D.
decreasing; increasing l-QUESTION:
88 L
Reactor power is increased sufficiently to cause steam blanketing l
of.several fuel rods.
This condition is being caused by:
m A.
departure from nucleate boiling.
i.,
B.
subcooled nucleate boiling.
C.
saturated nucleate boiling.
D.-
onset of nucleate boiling.
l t
-QUESTION:
89 l
Which.-one of the following incidents will cause the Departure from Nucleate Boiling Ratio-(DNBR).to INCREASE?- (Assume the f
reactor does not trip.).
l
'A.--
A reactor coolant' pump trips at'20 percent. reactor power.
L
- B.
A-rod (CEA)ndrops at 100. percent reactor power with manual-rod-(CEA). control.
i.
,C.
One steam dump valve rhils open at~50 percent reactor power.
4 D.
All. pressurizer' heaters energize fully at 40 percent reactor
. power.
FORM a 41 i
1
QUESTION:
90
~.How does critical heat flux vary from the bottom to the top of the. reactor core during normal full power operation?
A.
Decreases continuously.
B.
Decreases then increases.
C.
Increases continuously.
D.
Increases then decreases.
QUESTION:
91 The reactor coolant subcooling margin will be DIRECTLY REDUCED by:
L A.
increased pressurizer pressure.
L B.
increased pressurizer. level.
L C.
increaued reactor coolant flow.
D.
increased reactor coolant temperature.
l
' QUESTION:
92' Refer-to the drawing of a fuel rod and coolant flow channel :(see-figure 10).
i At 100 percent. reactor power, the GREATEST temperature difference-in a fuel channel radial temperature profile will occur across.
. the::
A..
fuel.
1
- B.
- ifuel-to-clad gap.
12.
zircalloy cladding.
D.-
flow channel boundary (laminar) layer.
FORM A 42 I
s 9
QUESTION:
93 Which one of the following must exist for natural circulation flow to occur?
A.
The heat source must be larger than the heat sink.
B.
The heat source must be located higher than the heat sink.
C.
The heat sink must be larger than the heat source.
D.
The heat sink must be located higher than the heat source.
QUESTION:
94 If-the reactor is operated within core thermal limits, then:
.A.
plant thermal efficiency is optimized.
B.
fuel cladding integrity is ensured.
C.~
pressurized thermal shock will be prevented.
D.
reactor vessel thermal stresses will be minimized.
FORM A 43
-=---
4 QUESTION -
95 Refer to the drawing of a fuel rod and cod *snt flow channel (see figure ll) at beginning of core life.
)
Given the following initial core parameters:
100 percent Reactor power
=
500' degrees F T,,g
=
T,,g,,ni,,gi,,
= 2500 degrees F What would the fuel centerline temperature be if, over core life, the total fuel-to-coolant thermal conductivity were doubled?
(Assume reactor power is constant.)
A.
1250 degrees F L
L.
B.
1300 degrees F C.
1400 degrees F D.
1500 degrees-F 1
l:
l I
QUESTION:'
96 Brittle fracture is the-fragmentation of metal result'.ng from the application of
' stress at relatively temperatures.
.A.
compressive; high B.
compressive; low C.
tensile; high D.
tensile; low FORM A 44
~
a QUESTION:
97 4
Which one of the following comparisons will result in a HIGHER probability of brittle fracture of the reactor vessel?
L A.
A high coolant oxygen content rather than a low oxygen content.
B.
A rapid 100 degrees F cooldown at a high temperature rather than at a low temperature.
C.
A high material strength rather than a high material ductility.
I D._
A high gamma flux rather than a high neutron flux.
QUESTION:.
98 A pressure stress applied to the reactor vessel is:
A.
compressive-at the inner wall, tensile at the outer wall.
B.
' tensile at the. inner wall, compressive at the outer wall.
.C.
tensile across the entire wall.
D.
compressive across the entire wall.-
L
. QUESTION:
95 Which one of t.he following irradiation sources most significantly 4
reduces'the d2ctility of the metal of a reactor pressure vessel?
. -r A.
' Beta.
B.
- Thermal neutrons C.
Gamma-D.
Fast neutrons FORM A 45
=
QUESTION:-
100 Pressurized thermal shock is a condition that can occur following a
of the reactor coolant system (RCS) if RCS pressure is rapidly A.
cooldown; decreased 1
B.
cooldownt' increased C.
heatup; decreased D.
heatup; increased i
~
r I
i 1.
L i
FORM A 46
,e.
.I.:
9 UNITED STATES NUCLEAR REGULATORY COMMISSION PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1990 - FORM B Please Print:
Name:
Facility:
i ID Number:
' Start Time:
Stop Time:
INSTRUCTIONS TO CANDIDATE Use the answer sheet provided.
Each question has equal point value.
A score of at least 80% is required to pass this. portion of the written licensing examination.
All examination papers will be collected 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, f
i SECTION-QUESTIONS.
% OF TOTAL SCORE i
THERMODYNAMICS 1 - 28 REACTOR THEORY 29 - 56 COMPONENTS 57 - 100 TOTALS
'100 i
All work done on this examination.is my own.
I have neither given nor received aid.
w; L
Candidate's Signature l:
l<
FORM B 1
l
INSTRUCTIONS FOR FILLING OUT THE ANSWER SHEET FOR THE OCTOBER 10, 1990 GENERIC _ FUNDAMENTALS EXAMINATION-STUDENT ENROLLMENT SIDE BLANK / TITLE WHAT YOU SHOULD FILL IN INSTRUCTOR' Write in the name of the nuclear plant you are presently 4
associated with.
CLASS Write in the type of facility sponsored training program you are currently enrolled in (e.g. R0, SR0 Upgrade, SR0 Instant,etc.) Do DI include requalification programs.
-STUDENT I.D.
A.five digit number.
This number is supplied by the NUMBER proctor.
If you don't know ask the proctor.
AREA CODE Enter the last three numbers of your facility's "50" docket numb 0r.
spaces.) (Write in the boxes and darken the corresponding PHONE NUMBER LEAVE BLANK LAST NAME/
Enter your last name, followed by a space, your first name,'
FIRST NAME/
-leave a space then your first initial.
(Write in the. boxes M.I.
-and darken the corresponding spaces.
CODE Enter the two letter core which applies to you from the table below.
CATEGORY CODE Formerly NRC -Licensed Personnel:
FORMER. LICENSE LICENSE CLASS Ji Reactor Operator-Reactor Operator RT 4
_ Senior Reactor Operator Senior Reactor Operator-ST Reactor Operator
. Senior. Reactor Operator RA NEVER NRC Licensed Personnel:
l
' LICENSE CLASS-
-Reactor Operator UR'
' Senior: Reactor Operator US TEST ANSWER SIDE'
.t
' BLANK / TITLE WHAT YOU SHOULD FILL IN I
ID NUMBER
- Write your ID number (the same one yo'u filled out on the_
,l other side.
1 TEST FORM Fill in the appropriate space. All tests are designated-either A or B form on the cover sheet.
EXAM FORM Fill in the 0,0,0 spaces.
~
RULES AND GUIDELINES FOR THE GENERIC FUNDAMENTALS EXAMIh'ATION During the administration of this examination the following rules apply:-
(1)
Print-your name in the blank provided on the cover sheet of the examination.
(2)
Fill in the name of your facility.
(3)
Fill in_the ID-Nuuber you,were given at registration.
(4)
Fill.in your start and stop times at the appropriate time.
(5)
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.
(6)}foranswersproperlymarkedonthissheet.
se only the answer sheet provided.
Credit will only be given, Follow tho instructions for filling out the' answer sheet.
'(7)
Scrap paper will be provided for calculations.
(8)
Any questions about an item on the examination should be directed'to the examiner only.
(9)
Cheating;on the examination will result in the automatic forfeiture of this examination.
Cheating could also' result in severe penalties.
.(10) 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 H
3 of the examination room.
(11) After'you have completed the examination, sign thefstatement 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.
['
'(12)' Turn in your examination materials, answer sheet on top, followed by the exam booklet, then examination aids -= steam m'
Ltable booklets, handouts and scrap paper used during the examination.
'(13). After turning in your examination materials, leave the h
examination area, as defined by.the examiner.
If after leaving you are found in the examination areaLwhile the examination is.in progress, your examination may be forfeited.
FORM B I..
1 e
i CENERIC FUNDAMETALS EXAMINATION SECTION EQUATIONS AND CONVERSIONS HANDOUT SHEET i
EQUATIONS 6
- ac AT Cycle Efficiency Net Vork (out) p Energy (in) 6 a Ah SCR S/(1. K,gg) 6 UA AT CRg (1. E,gg)g CR2 (1
- Keff)2 SUR - 26.06/r M
1/(1 K,gg)
CR /CR g
0 26.06 (A,gg p)
(1 K,gg)g (3.p)
(1. K,gg)g SUR(t)
E P 10 seg (1, geff)fgeff a
IE/#}
P P, e Pwr W a g
(1*/P)+[(h*#)/A,gg#)
1*/(P ' 4) f f
=
i i
(K,g,,,. 1)/K,gg 1*
1 x 10 5 seconds e
'* If/K.gf A,gg - 0.1 seconds'1 v(P, - P ) + 1 I
'V 2
- 2)
- III ~#)=0 3
2 e
i e
1 i
l=
CONVERSIONS 10 1-Curie 3.7 x 10 dps 1 kg 2.21 lba 1 hp 6
2.54 x 10 BTU /hr 1 Mw 3.41 x 10 BTU /hr 1 BTU 778 f t lbf
- T 9/5 'C + 32
'C 5/9 ('T - 32) 1 i
l
j l
1 I
l l
l S
{]
AIR SUPPLY m
o VENT l
\\
t r
s e
i l
_w
)
l SPRING LOADED AIR OPERATED VALVE l
FIGURE 1 i
{
l
- -- - * +=* -
g
d REFERENCE LEG FILL CONNECTION t-OR VA PRESSURE h
}
l WATER EQUALIZING VALVE D7 ss s
/
D/P DETECTOR TANK DIFFERENTIAL PRESSURE !,EVEL DETECTOR FIGURE 2 4
1 N
4 e
(
PRESSURIZER CONDENSING POT
. STEAu.
C EOUALl2iNG
/
/
VALVE WATER
/
L 7
ms D/P DETECTOR PRESSURIZER DIFFERENTIAL PRESSURE LEVEL DETECTOR FIGURE 3
=
,' STEAM CONDENSING POT
.Q G.
/
/
/
/
EQUALIZING p
VALVE
/ WATER
,/
r
~,
/
/
D/P
~~~7-~~
DETECTOR I
I I
I STEAM GENERATOR DIFFERENTIAL PRESSURE LEVEL DETECTOR FIGURE 4
ll l!ll S
L F
O G R GWO LM I
C C L
8jI C
O C S
O G O U
s*
q t
PA J
I J
CT J
VI I
P RL
/
g E P R
L S O Y
A R
I T
GL T
E P
N A
M P
R N
A O
O LR E
S SV P
i :
IT A U
u.
H L" r OV L
M I
E A
R NE T
m E
E C
I P
a R
R u
L O F
F C
O T I
I R
G O
S E
U OG Il N
C O l
I T
CTM R
E FF O
I R
ER N
5 O
EO L
DM S
Y S
T U
E C
M O
N T
R O
L
- [-:E.
VA LV E
I STE T A O M
ll lli1 lli j
!f!
lf1j;jlI
{l{
l
SPRING f FLYBALL FULCRUM y
&Y t
7 L
[.'M T
4 r
FUEL ON a
FULCRUM S
FUEL OFF 4
s b
9 FUEL PIPE FLYBALL WEIGHT MECHANICAL SPEED GOVERNOR b
FIGURE 6
1 4
6
^
HEAT EXCHANGER t
l 4
' O PUMP i
COOLING WATER SYSTEM FIGURE 7
2
+=
Ad m---e M
~
s a
m--
a=2
---a--*
0 4
4
-~- - - -
^ ^
HEAT EXCHANGER
' O PUMP A
^ O PUMP B COOLING WATER SYSTEM FIGURE 8
t LP FLUID TANK 90'F v
l 120*F FAILED TUBE HP FLUID 0
PUMP COOLING WATER SYSTEM FIGURE 9
~. _. _. _ _. _ _ _ _ _. _ - _..
4 j
w w
2 CLAD e
l m
=
w.
J I
I*
FUEL PELLET l
w l J I
y F
l 7
w s
i e
l l
o n
W t J l
' r lm e
.2 e-1 I
COOLANT l
COOLANT s
- p u is k
FLOW FLOW
's,u l
s.
l l
s FUEL ROD AND COOLANT FLOW CHANNEL i
FIGURE 10 l
}
l
. -..,, - ~ ~
,---n-
i i
1 l
4 CLAD r l m w
2 I
I FUEL PELLET
=
s l
< t J I
m r
- s u
I l
l K
n n
l e n
_J I
a
'J F
D t
e
.J j
I j
i l
e l
COOLANT l
E COOLANT FLOW f
u is FLOW 9
l s)
I l
FUEL ROD AND COOLANT FLOW CHANNEL 1
i FIGURE 11 l
- ~ - - -
QUESTION:
1 Assuming an atmospheric pressure of 15 psia, 5 inches of Mercury (Hg) vacuum is equivalent tot A.
2.5 psia.
B.
5.0 psia.
C.
10.0 psia.
D.
12.5 psia.
QUESTION:
2 If condensate temperature in the hotwell is 6 degrees F subcooled with a temperature of 112 degrees F,
what is the condenser pressure?
A.
1.1 psia B.
1.4 psia C.
1.6 psia D.
1.9 psia QUESTION:
3 Condensate depression is the process of A.
removing condensate from turbine exhaust steam.
B.
spraying condensate into turbine exhaust steam.
C.
heating turbine exhaust-steam above its saturation temperature.
D.
cooling turbine exhaust steam below its saturation temperature.
FORM-B 3
QUESTION:
4 The plant is maintained at 2,000 psia with a pressurizer temperature of 636 degrees F.
A pressurizar 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?
A.
280 degrees F B.
240 degrees F C.
190 degrees F D.
170 degrees F QUESTION:
5 Condenser pressure is 1.0 psia.
During the cooling process in the condenser the LP turbine exhaust temperature decreases to 101.0 degrees F, at which time it is at A.
saturated liquid.
B.
saturated vapor.
C.
subcooled liquid.
D.
superheated vapor.
QUESTION:
6 To achieve maximum efficiency, feedwater should enter the steam generator and the temperature difference across the tubes should be as as possible.
A.
close to saturation; small B.
close to saturation; great C.
as subcooled as practical; small D.
as subcooled as practical; great FORM B 4
i
i QVESTION:
7 A centrifugal pump is being returned to service after maintenance.
The operator FAILS to vent the pump properly.
When the pump is started the operator should see capacity and discharge head.
A.
lower; lower B.
lower; higher C.
higher; lower D.
higher; higher QUESTION:
8 The major concern with starting a feedwater pump with downstream fluid in a saturated condition is:
A.
cavitation.
B.
C.
thermal shock.
D.
positive reactivity addition.
1 l
QUESTION:
9 While on surveillance
- rounds, an operator notices that a
centrifugal pump is making a great deal of noise (like marbles rattling inside the pump casing) and the discharge pressure is fluctuating.
This set of conditions indicates:
L A.
excessive pump discharge pressure.
B.
pump runout.
C.
pump cavitation.
D.
FORM B 5
l l
l
QUESTION:
10 Flow instruments used to measure the mass flow rate of saturated steam are density compensated because, for a steam pressure increase at a constant volumetric flow rate, steam density will
_,and the actual mass flow rate will A.
dectusset increase B.
increase; decrease C.
increase; increase D.
decrease; decrease QUESTION:
11 To decrease the flow rate through an operating positive displacement pump, an operator should:
A.
throttle the pump discharge valve.
B.
throttle the pump suction valve.
C.
decrease the pump NPSH.
D.
decrease the pump speed.
QUESTION:
12 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.
FORM B 6
QUESTION:
13 The reactor is operating with the following parameters:
Reactor power - 100 percent Core delta-T 42 degrees F RCS flow rate - 100 percent Average coolant temperature - 587 degrees F A station blackout occurs and natural circulation is established with the following stable parameters:
Decay heat - 2 percent Core delta-T - 28 degrees F Average coolant-temperature - 572 degrees F What is the core mass flow rate in percent?
A.
2.0 percent B.
2.5 percent C.
3.0 percent D.
4.0 percent i
QUESTION:
14 As heat is transferred to s'ater adjacent to a heating surface, j
many factors influence steam bubble formation.
Select the i
characteristic below that will ENHANCE steam bubble formation.
A.
Chemicals dissolved in the water.
B.
The absence of ionizing radiation exposure to the water.
C.
A highly polished heat transfer surface with minimal scratches or cavities.
D.
The presence of gases dissolved'in the water.
FORM B 7
4
QUESTION:
15 Nucleate boiling enhances the convective heat transfer coefficient by the thermal conductivity of the coolant and the laminar layer thickness.
A.
increasingt decreasing B.
increasing; increasing C.
decreasingt decreasing D.
decreasingt increasing QUESTION:
16 Reactor power is increased sufficiently to cause steam blanketing of several fuel rods.
This condition is being caused by:
A.
departure from nucleate boiling.
B.
subcooled nucleate boiling.
C.
saturated nucleate boiling.
D.
onset of nucleate boiling.
QUESTION:
17 Which one of the following incidents will cause the Departure from - Nucleate Boiling Ratio (DNBR) to INCREASE?
(Assume the reactor does not trip.)
A.
A reactor-coolant pump trips at 20 percent reactor power.
B.
A rod (CEA) drops at 100 percent reactor power with manual rod (CEA) control.
C.
One steam dump valve fails open at 50 percent reactor power.
D.
All pressurizer heaters energize fully at 40 percent reactor power.
l FORM B L
8 l
t QUESTION:
18 How does critical heat flux vary from the bottom to the top of the reactor core during normal full power operation?
l A.
Decreases continuously.
B.
Decreases then increases.
t C.
Increases continuously.
D.
Increases then decreases.
l l
l QUESTION:
19 l
l The reactor coclant subcooling margin will be DIRECTLY REDUCED byt A.
increased pressurizer pressure.
D.
Increased pressurizer level.
C.
increased reactor coolant flow.
D.
increased reactor coolant temperature, j
L QUESTION:
20 Refer to the drawing of a fuel rod and coolant flow channel (see figure 10).
At 100 percent reactor power, the GREATEST temperature difference in a fuel: channel radial temperature profile will occur across that A.
fuel.
B.
fuel-to-clad gap.
C.
zircalloy cladding, i
D.
flow channel boundary (laminar) layer.
FORM B i
9
QUESTION:
21 Which one of the following must exist for natural circulation flow o occur?
l A.
The heat source must be larger than the heat sink.
B.
The heat source must be located higher than the heat sink.
C.
The heat sink must be larger than the heat source.
D.
The heat sink must be located higher than the heat source.
QUESTION:
22 If the reactor is operated within core thermal limits, then:
A.
plant thermal efficiency is optimized.
B.
fuel cladding integrity is ensured.
C.
pressurized thermal shock will be prevented.
D.
reactor vessel thermal stresses will be minimized.
FORM B 10
QUESTION:
23 Refer to the drawing of a fuel rod and coolant flow channel (see figure 11) at beginning of core life.
1 Given the following initial core paiameterst i
Reactor power 100 percent
=
ewlm 500 degrees F T
=
T,,,g,,t
= 2500 degrees F ng,,gi,,
What would the fuel centerline temperature be if, over core life, the total fuel-to-coolant thermal conductivity were doubled?
4 (Assume reactor power is constant.)
i A.
1250 degrees F B.
1300 degrees F C.
1400 degrees F D.
1500 degrees F QUESTION:
24 Brittle fracture is the fragmentation of metal resulting from the application of stress at relatively temperatures.
A.
compressive; high B.
compressive; low C.
tensile; high C P CPWrt D,
tensile; low
)
FORM B 11
i i
l QUESTION:
25
. Which one of the following comparisons will rasult in a HIGHER probability of brittle fracture of the reactor 'ressel?
A.
A high coolant oxygen content rather than a low oxygen content.
l B._
A rapid 100 degrees F cooldown at a high temperature rather than at a low temperature.
i."
C.
A high material strength rather than a high material ductility.
l D.
A high gamma flux rather than a high neutron flux.
l QUESTION:
26 l
A pressure stress applied to the reactor vessel ist A.
compressive at the inner wall, tensile at the outer wall.
i i
B.
tensile at the inner wall, compressive at the outer wall.
1 l
i L
C.
tensile across the entire wall.
D,--compressive across the entire wall, j
l QUESTION:
27 1
1 Which one of the following irradiation sources most significantly reduces-the ductility of the netal of a reactor pressure-vessel?
]
.A.
Beta l
r B.
Thermal neutrons C.
Gamma D.
Fast neutrons FORM B 12 j
QUESTION:
28 Pressurized thermal shock is a condition that can occur following a
of the reactor coolant system (RCS) if RCS pressure is rapidly A.
cooldown; decreased B.
cooldown; increased C.
heatup; decreased D.
heatup; increased I
?
k i
FORM B 13 t
o 1
QUESTION:
29 i
Which of the following conditions describes a reactor that is EXACTLY critical?
)
A.
K,,, = 17 delta-K/K = 0 B.
K,,, = 17 delta-K/K = 1 C.
X,,, = 0; delta-K/K = 0 D.
K,,, = 0; delta-K/K = 1 l
QUESTION:
30 with K,,, =.0.987, how much reactivity must be added to make j
the reactor exactly critical?
i A.
1.30% delta-K/K B.
1.32% delta-K/K C.
1.34% delta-X/K D.
1.36% delta-K/K I
f FORM B 14
.J
QUESTION:
31 A reactor is operating at steady-state 90 percent power with
. all control rods (CEAs) fully withdrawn and T,, at 580 degrees F.
A reactor trip occurs, after which T*
stabilizes at 550 degrees F and all rods (CEAs)are verified to be fully inserted.
Given the following information, calculate the value of shutdown margin.
Assume no operator actions and disregard any reactivity effects of xenon.
Power coefficient = -0.01% delta-K/K/% power Control / Regulating Rod Worth = -2.788% delta-K/K Shutdown / Safety Rod Worth = -4.130% delta-K/K MTC = -0.01% delta-K/K per degree F A.
-5.718% delta-K/K B.
-6.018% delta-K/K C.
-7.518% delta-K/K D.
-7.818% delta-K/K 4
QUESTION:
32 A suberitical reactor has an initial source /startup range count rate of 150 cps with a shutdown reactivity of -2.0% delta-K/K.
How much positive reactivity.aust be added to, establish a stable count rate of 300 cps?
A.-
0.5% delta-K/K B.
1.0%. delta-K/K C.
1.5% delta-K/K D.
2.0% delta-K/K FORM B 15 r
6
l l
l l
i-l QUESTION 33 l
Which one of the following conditions will initially result in a positive startup rate when the reactor is at power?
A.
Increase in turbine loading l
B.
Unintentional boration C.
Turbine runback D.
Accidental closure of a main steam isolation valve L,
o QUESTION:
34 e
l.
Moderator temperature coefficient will be LEAST NEGATIVE at a l
reactor coolant temperature and a reactor coolant boron concentration.
L i
A.
low; low 1-B.
high; low C.
low; high-I D.<
hight high t
li 3
QUESTION::
35 The amount of boric acid required to increase the coolant boron concentration by 50 ppm at BOL conditions (1200 ppm) is approximately.
as the amount of boric i
acid required to increase boron: concentration by 50 ppm at L
-EOL (100 ppm).
A.
twelve times as large
.B.
eight times'as large C.
-four times as large D.
the same FORM B 16 t
t -
3,-
.v..
QUESTION:
36 The plant is being returned to operation foll ving a refueling outage.
Fuel preconditioning requires reactor power being increased from 10 percent to full power gradually over a ONE WEEK period.
During this slow power increase, most of the positive reactivity added by the operator is required to overcome the negative reactivity from:
A.
fuel burnup.
B.
xenon buildup.
C.
fuel temperature increase.
D.
moderator temperature increase.
I o
L QUESTION:
37 L
Which one of the following statements concerning the power defect is correct?
The power defect necessitates the use of a ramped T., ling A.
program to maintain an adequate Reactor Coolant System subcoo margin.-
j B.
The power defect increases the rod (CEA) height requirements necessary to maintain the desired shutdown margin following a reactor trip..
C.
The reower defect is more negative at the beginning of core 0
lifo because of the higher boron concentration.
j l
D..
The power defect causeo control rods (CEAs) to be withdrawn'
=!
l:
as reactor power is-decreased.
j L
I
.q i
l FORM B 17 1
'l
-l
~ --
l QUESTION:
38 i
' Differential rod worth will be the greatest if RCS temperr.ture is and RCS boron concentration is A.
increased; decreased B.
decreased; decreased C.
increased; increased D.
decreased; increased L
QUESTION!
39 Which one of the following describes why most of the power is produced in the lower half of a core that has been operating at 100 percent power for several weeks at the beginning of core life?
A.
Xenon concentration is lower in the lower half of the Core.
B.
The moderator to fuel ratio is lower in the lower half of the i
core.-
l C.
The fuel loading in the lower half of the core contains a L
higher U-235 enrichment.
D.
The moderator temperature coefficient of reactivity is adding less negative reactivity in the lower half of the core.
i l
r 1g fl l:
l' 1,
s l
FORM B l-18 1
1
l, lOUESTION:
40
.The basis for the maximum power density (kw/ft) power limit is to:
A.
l provide assurance of fuel integrity.
B.
prevent xenon oscillations.
1 C.
allow for fuel pellet manufacturing tolerances.
D.
prevent nucleate boiling.
QUESTION:
41 (The plantsis; operating at equilibrium 30 percent power level at
.EOL-with all control. rods (CEAs) fully withdrawn.
If control rods (CEAs) are-partially: INSERTED, the axial neutron flux will shift-from the of the reactor core.
A.
Itop toethe; middle
'B.
-middle to the bottom-C.
. middle to the top m;
'D.-
bottom to the middle i
fi U N
U
- QUESTION:-
42
,o
-Two'cNaracteristics of Xe-135 that result ~in-it being-A MAJOR-reactor; poison lare its,relatively' half-liferand relatively
. absorption cross section.
A.-.'short; large ib
=
small
'LB.-
short; l:
c, C.
Ilong;11arge
[-
_D,,-long;Lsmall'-
e FORM B 19 i,,~
' y.
i
s.
u-e QUESTION:'
43 Two identical reacto::s have been operating at'a constant power aeyel for one week.
Reactor A is at 50 percent power and Reactor B is. at 100 percent power.
If both reactors trip / scram at the same time, xenon-135 will peak first in reactor and the highest
-xenon-135 reactivity peak will occur in reactor A.
At A B.
A; B C.
B; A D.
B; B QUESTION:
44 Reactor power is increased from 50 percent-to 60 percent in one hour..
The most significant contributor to the. initial change'in
. xenon' reactivity is the increase in:
t A.
! xenon production.from fission.
4 C.
xenon absorption of neutronc.:
D.
xenon' production from iodine' decay..
f 1
l
)
?
f FORM B 20 a
i
~.-
i
\\=
i QUESTION:
45 A reactor has been operating at 50 percent power for a week when power is quickly ramped (over 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) to 100 percent.
How will the xenon concentration in the core respond?
A.
Decreases initially, then builds to a new equilibrium concentration in 8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
B.
Increases steadily to a new equilibrium concentration in 20 J
to 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
C.
Decreases initially, then builds to a new equilibrium 1
concentration in 40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
D.
Increases steadily to a new equilibrium concentration in 60 to 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br />.
QUESTION:-
46-fi-'
- A reactor that has been operating at rated power for about two weeks reduces power-to 50 percent.
Xenon-135'will reach a new (equilibrium condition in houro.
A.
t 8 to 10 4
B.
20 to 25 1C.
30 to 35
- w i
. '40 to_50
.D.
_q
.4
)
?'
e 3
' 'l%
ik Ad!T p>+
m!il
>q, s.
~t FORM B 21
.i.
!k
![
i 1
}
QUESTION:
47 6
A reactor has been operating at 100 percent power for several weeks with power production evenly distributed-axially above and below the core midplane.
Reactor power is reduced,to 50 percent using boration to control T,, while maintaining control rods (CEAs) fully withdrawn.
The axial power distribution will:-
-A.
shift-toward the top of the core.
B.
-shift toward the bottom of the core.
C.-
remain evenly' distributed above and below the core midpinne.
D.
-peak at the top and the bottom of the core.
o.
- QUESTION
48 During a
six-month period of continuous full power reactor operation, the RCS boron concentration must be decreased steadily to_ compensate for:
A.
buildup of. fission product poisons and burnable poison burnout.,
B.
fuelldepletion'and buildup of: fission product poisons.=
lC ;- ; decreasing! control rod (CEA) worth and burnable poison burnout.
D.
burnable _ poison burnout and fuel depletion.
t i
FORM B 22 i
I QUESTION:
49 While withdrawing control rods (CEAs) during an approach to criticality, the-stable count rate doubles.
If the same amount of reactivity that caused the first doubling is added again, stable count rate will-and the reactor will be A.
increase but not double; subcritical B.
double; subcritical C.
double; critical h
D.
more than double; critical QUESTION:
50
'During.a reactor startup, as K,n increases toward criticality,
-the value of 1/M:
-A.
decreases toward zero.
.B..-
decreases toward one.
C.-
increases toward-infinity.
D.
increases toward one.
m r
FORM B 23'
'Y
^
QUESTION -
51 An estimated critical rod position (ECP) has been calculated for a reactor startup that is to be performed 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a trip from a 60 day full power run.
Which one of the following events or conditions will result in the actual critical rod position being LOWER =than the ECP?
A.
The startup-is_ delayed.for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
B.
The main steam header pressures are decreased by 100 psi just prior to criticality.
C.
A new boron sample shows a current boron concentration 20 ppm higher than that used in the ECP calculation.
D.
Steam generator feedwater addition rate is reduced by 5 percent just prior to criticality.
QUESTION:
52 Which of the following, if changed, will have the MOST SIGNIFICANT-effect on reactivity while the. reactor is critical below the point i
of adding heat?
m A.
Coolant 1 temperature and rod (CEA) position B.-
Coolant: temperature and coolant pressure C.
' Rod [(CEA). position'and reactor power
.b.-
Coolant pressure and reactor power f
a i
5>
3 f
a)
FORM B 24 g"Y 1
3 g
1 i
i i
QUESTION:--
53 A reactor is subcritical by 1.0% delta-K/K.
The_ operator dilutes the RCS by 30 ppa boron.- Assuming boron worth is 0.025% delta-K/K
~
per ppa and that no other reactivity changes occur, the reactor is:
A.
suberitical.-
B.
critical.;
C.
supercritical.
l
.D.
prompt critical.
QUESTION:
54 A reactor startup_is being performed following a one-month shutdown period.- If the reactor is taken critical and:then-stabilized at
-10,000fcps;in the source /startup range, over the next 10 minutes
~
the count rate will:
A.
remain' constant.
-B.;idecrease linearly.
C.
idecrease' geo:netrically.
D.
, decrease exponentially.
T
- QUESTION:
55 3
Alreactor is' operating just above the pointfof adding heat.
In orderl to'. raise reactor: power to a higherL stable power level, the operat'or must1 increase:-
A.
ste,am generator levels.-
LB..' steam demand.
C..
Tg.
D.- - reactor coolant system boron concentration; FORM B 25 i
!9L QUESTION:
56 The magnitude of decay heat generation is determined primarily by:
A.-
core burnup.
j.
L B.
power history.
c; final power at shutdown.
4 D.
control rod worth at shutdown, p_
f
.,.p
[
'I h
ii-1
. ! 'i
- JH '
li k.j V o, t
'I'~
i,
{ yrs utj g
j
'e ( li n,. :;;
y-_
.' Yl i
I MR.
i t ' 'l
,. i s:
8 m
u 4
., ;l;:,
.O!D..
e
(!1?~
li-1 0 ; ' i?!
- 1 k
b FORM B H'
'26 x.
.k;-
h(;i[.
- +,
s')ki.! '.
idiVR:4
J
- QUESTIONI.
57' Refer to the drawing' of a spring-loaded air-operated valve (see figure 1).
Upon a loss offair pressure, this valve will:
A.
go to the fully open position.
B.
remain at the current position.
C.
go to the fully closed position.
-D.
go to the mid-position.
1 QUESTION:
58 l
Operators;should use BOTH hands on valve handwheels when positioning LARGE~ manual valves to:
.A.
overcome the resistance of installed locking' devices.
B; -control the rate of valve: motion to prevent water hammer.
C.
= ensure system pressure, temperature, and flow are controlled during valve motion.
D.
control' lateral. force to prevent bending the valve stem.
R QUESTION:'
59-When: manually positioning a motor-operated valve,. care must
'be=takenito avoid usingcexcessive~ valve seating /backseating t
tforce because:-
' A.,
the' valve might not operate on demand.
1 B.
- torque switch settings may change.
'C.
. limit switch settings may-change.
3 D..
the valve motor will_not reengage.
FORM B 27
=
=
. QUESTION:
60
-To verify L a manual valve in an operating system is closed, the operator.should operate.the valve handwheel in the:
-A.
open direction until the valve is fully open, then reclose it'using normal force.
B.-
close direction using nor9a1 force'and verify there is no substantial handwhee)-movenant.
-c.
-open. direction until'ilow sounds are heard, then r
reclose the valve' s ing normal force.
D.
close directior,until it' stops, then close it an c
additional one.-half turn using additional force if necessary, i;
QUESTION:,
61 When comparingcthe characteristics of, gate and globe valves in an operating system, n globe valve generally -has the pressure drop" when fully open' and is the better valve for-flow.
A.
lower;; isolating.
B '. -. higher;; isolating C.
lower;Lthrottling DJ higher;cthrottling m
f if j
s9
.g;. :
l' FORM B 28 v
l 1
L-i r
.tri
- p V
-QUESTION:
62' The. density compensating input to a steam flow instrument is used to convert volumetric flow rate to:
A.
velocity flow-rate.
B.
gallons'per minute.
c.
mass flow rate.
D.
differential' flow rate.
e M.
x
-QUESTION:-
63 y
i If the liquid flowing through'a' differential pressure liquid flow rate detector contains entrained = voids -(gas or steam), indicated
, s
.c
' flow rate-will be:
1 flf m
, [Ai erroneously high.-
q
+
B.~
> erroneously-low..
'i c.
unaffected.
'e 1
D.
Efluctuating.
- [
+,(
1 n
%(
c
}t y
F QUESTION:
.64-i.
Which of the following will_.cause indicated volumetric flow rate.
to.be'LOFER than actual volumetric flow rate using a differential' pressure (D/P) flow detector and a calibrated orifice?
w L
A.
Debrio'becomes lodged'in the-orifice.
B.
-A leak developsLin-the low pressure: sensing'line.
[m3 p
c.
The orifice' erodes over time.
l l;
D.- 'Systemjpressure decreases, b.
J I
LFORM B 29 l*
i i
4 1
- 1 QUESTION f 65 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 squared.
t y
i B~
INVERSELY proportional to the differential pressure squared.
DIRECTLY proportional to the square root of the C..
differential pressure.
' 1 D.
INVERSELY proportional to the square root of the.
differential pressure.
]
+
QUESTION:-
66 Refer to.the drawing of a tank differential pressure level detector
- (see : figure 2).
If: the differential; pressure detector equalizing valve is opened,
- level ' indication will:
i A '.'
decrease and stabilize >below actual' level.
- B.;
increase and' stabilize above actual level.
C.
oscillate aboveland below actual level.-
1 D.-
-remain constant'at the current level.
7 e
r
't:
~
[-
i i
u l
'1 FORM'B 30 l
l.
E '
rp.
QUESTION:
67 Refer to the drawing-of a pressurizer differential pressure-level detector (see figure 3).
With the plant at normal operating conditions, a pressurizer level
' differential pressure (D/P) instrument, that had been calibrated while the plant was in a
cold condition, would indicate
-than actual level because of a differential pressure sensed by the D/P-detector at normal E
operating conditions.
A.
_ lowers: larger B.-
lower; smaller C.
higher; larger D.
higher; smaller
\\
_ QUESTION:
- 68 Refer = to 'the : drawing 'of a = steam generator dif ferential L pressure level detector-(see figure 4).
.Which one of the following failures will-cause the associated steam
.y generatornlevel' indicator to indicate the LOWEST level?
-A.
1The D/P detector. diaphragm: ruptures.
B.
The: reference leg ruptures.
C.
The variable leg ruptures.
D.
The equalizing valve is opened.
g, i
FORM B 31 t
i k
\\
t..
QUESTION:
69'
'If the pressure sensed by a bourdon tube increases, the curvature of the detector will because of the greatest force being applied.to the curve of the detector.
A '.
increase; inner B.., decrease; inner C.
increase; outer D.
decrease; outer QUESTION:
= 70
_If a resistance temperature detector (RTD) develops an OPEN circuitL(bridge circuit remains intact), indication'will fail:
A.
high.
- B.
low.-
.C..
,as is.
D.'
- to mid-scale._
j i
\\
FORM B 32 1
h
' QUESTION:
71 The plant has experienced a loss of coolant accident (I4CA) with degraded safety injection flow.
The reactor coolant pumps (RCPs) have been manually tripped and the resulting phase separation caused,the. upper portion of the core to uncover (approximately 20 percent).
.Which,one of the following describes excore source /startup range
. neutron level indication following the core uncovering, relative-to the indication just prior to the core uncovering?
A.
.Significantly less
'E.
Significantly greater C.
Essentially unchanged D..
Impossible to estimate with the given~ core conditions.
QUESTION:
72
-Which type of. radiation-detector is generally used to perform a survey in a. IDW level' gamma radiation area? '
'A.
Ion chamber.
B.
Geiger-Mueller-i C.
Proportional'
'D.-
Scintillation 1
r i
FORM B 33
5
'k!
9
. QUESTION:
73 IfLthe turbine shaft speed signal received by a typical turbine governor control system fails low during turbine startup, the turbine governor will cause-turbine speed to:
A.
increase, until an upper limit is reached or the turbine trips on overspeed.
B.
decrease, until the mismatch with demanded turbine speed is
- nulled,
- c. - decrease to minimum speed.
'D.
cycle approximately 5 percent above and below the current
- speed, o
h u
. QUESTION:
_74' l
' Refer to the drawing ~of a= pneumatic control system (see figure 5).
-The purpose'of'the valve' positioner is to convert:-
a small' air pressure'into a_ proportionally larger air A..
pressure to adjust: valve position.
B.
a.large air pressure into a proportionally smaller air
,. s #
pressure'to adjust valve position.
- p p
c.
pneumatic force ~into mechanical force to adjust valve.
position._
' 4 2-
-D; mechanical' force into pneumatic force to adjust valve (W
position.
'n-
- i v.
5 S!!'
t
'3 j
FORM B 34 i
a#
i i
I j!
L QUESTION::
75
{
Refer to the drawing of a flyball-weight r echanical speed governor l
o (see figure 6).
l l
In a flyball-weight mechanical speed governor, the purpose of the spring on the flyball mechanism is to:
l A.
counteract centrifugal force by driving the flyballs apart.
i B.
aid centrifugal force by pulling the flyballs together.
c.
counteract centrifugal force by pulling the flyballs together.
D.
aid centrifugal force by driving the flyballs apart.
-QUESTION:.
76 i
What precaution must be observed when transferring a valve l
controller from the automatic mode to the manual mode of control?
I l
A.
Ensure that the; proper offset is established between the l
automatic mode and: manual mode.
l B.
Ensure that:the valve controller output signals are matched'between automatic mode and manual mode.-
C.
Ensure th'at the automatic valve controller signal is 1
- decreasing'before transferring to the manual mode of j
control.-
j 1
D.
Ensure that the automatic valve controller signal is increasing before transferring to manual mode of j}
control.
i j
1 l
4 FORM B I
35 l
t a
QUESTION:
77 Pump cavitation occurs when vapor bubbles are formed at the eye of a pump impeller:
A.
when the localized flow velocity exceeds sonic velocity for the existing fluid temperature.
B.
when the localized pressure exceeds-the vapor pressure for the existing fluid temperature.
C.
and enter a high pressure region of the pump where they collapse causing damaging pressure pulsations.
D.
and are discharged from the pump where they collapse in downstream piping causing damaging pressure pulsations.
. QUESTION:
78
'The presence of air in a pump casing may result in when the pump is started..
t 7
A.
vortexing.
i B.
. pump runout C.
pump'overspeed D.
gas binding t
QUESTION:
.79 operating-a motor-driven centrifugal pump-for an extended period of.
. time under no flow' conditions will cause:
A.
pump failure from overspeed.
B.
pump failure from overheating.
C.
motor failure from overspeed.
D.
motor failure from overheating.
FORM B 36 i
t
.~
-QUESTIONt.
80
-Refer to the drawing of a cooling water system (see figure 7).
-The centrifugal pump is circulating water at 100 degrees F.
After several hours the water temperature has increased to 200-degrees F.
Assuming. system flow rate (gpm) is constant,_ pump motor amps will have because
'A.
decreased; water density has decreased B.
increased; water density has decreased C'
decreased: pump shaft speed has increased D-increased; pump shaft speed has increased QUESTICN:
81 Refer;ts the drawing of'a cooling water system (see figure 8) in which pumps A and'B are identical single-speed centrifugal pumps.
~ Compared to system ~ operating conditions with only pump A operating, af ter. pump B.is started, system flow rate will be 'approximately and: pump discharge pressure -will be approximately A.'
constant; double B..
double; constant.
C.-
' constant;' constant i
D.
double; double
, L 4
FORM B 37 I
i
, QUESTION:
82
- If the speed of a positive displacement pump is increased, the available net positive suction head (NPSH) will and the probability of cavitation will A.
decrease; not change B.
not change; decrease C.
increase; decrease D.
decrease; increase QUESTION:.
83 An ' operator can-dif ferentiate a locked reactor coolant pump (RCP) rotor from a sheared RCP rotor 30 seconds after the event by the:
(Assume no' operator action.)
A.
loop flow indications.
B.-
RCP ammeter indications.
C.
loop differential temperature indications.
D..
reactor trip status.
s
' 1 FORM B 38
,.,,4-
...:,...:....:...w
')
9.
i QQESTION:
84 A' centrifugal pump is operating at 600 rpm with the following parameters:
Current = 10 amperes Pump. Head = 50 psi Pump Flow Rate = 200 gpm What will be the new value of pump head if the flow is i
increased such that the current requirements are now 640 amperes?
'A..
400 psi B.
600 psi i
C.
800 psi D.
1,200 psi
~ QUESTION:
85
~Iflthe discharge valve of a large AC motor-driven centrifugal pump remains closed during a normal pump start,.the motor ammeter indication will rise to:
A.
.several times the full-load: current value and then decrease to the no-load current value.
B.
- approximately the full-l'oad current value and then i
' decrease to the no-load. current,value.
'C.:
several times the full-load current value and then
-decrease to the full-load.value.
. D.-
approximately the full-load current value and then.
stabilize at the full-load current value.
3
,f' u
L:
-FORM B 39 o
[;
i I ]fl
1 QUESTION:
86 I
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 due to high starting currents.-
B.
rotor damage can occur due to excessive cyclic stresses on the shaft.
I
- c. -overheating of the windings can occur due to shorting within
'l the stator.
j D.
rotor damage can occur.due to excessive. axial displacement of j
the shaft.
]
I i-s 1
!q QUESTION:
87 l
A1 main generator.is operating on the grid with the following indications:.
]
]
'100'MWe-
- 0 MVAR.
- 2,800 amps
(
- 20,000 volts
).
If, main generator excitation'is reduced, amps will and
- MWe will
,l
'1 A.
decrease; decrease i
B.. Jincrease; decrease C.
decrease;tremain the same D..
increase;:romain!the same a
')
FORM B 40 l
T l
QUESTION:
88 Whenever possible, a heat exchanger should be placed in service by introducing both fluids gradually and simultaneously to:
A.-
prevent excessive thermal stresses in the heat exchanger.
B.
maximize the heat transferred across the heat exchanger tubes.
c.
minimize boiling of the cooling water in the heat exchanger tubes.
D.-
provide maximum temperature control of.the system being
- cooled, n
QUESTION:
-89 Tube scaling in a parallel-flow heat exchanger will cause heat transfer to decrease because:
A.
flow through the heat exchanger increases.
B.
surface area of the tubes decreases..
- c. ' heat transfer coefficient decreases.
D.
-inlet temperature of the cooling fluidLincreases.
1 FORM B 41
- i
3 t
(
4 -
. QUESTION:4 90 t
Refer toithe. drawing of an operating cooling water system (see figure 9).
Which'of'the following effects would occur as a result of a tube FAILURE in-the heat exchanger?
A.
High pressure fluid flow rate decreases.
B.
Flow in the low pressure system reverses.
5 C..
Temperature in the low pressure system increases.
D.-
Level in the tank' increases.
l t
I QUESTION:
- 91 The purpose of a demineralizer is to:
A.-
raise the conductivity of water without affecting.pH.-
1 B.-
reduce ~the. conductivity of water without affecting pH.
i l
C.
increase the'pH of water by reducing the number of j
f_ 4 (positively charged ions in it.
p' j
D.
decrease the pH of water by-increasing the number of j
negatively charged ions in it.
ts L
' QUESTION:
92 i
Prior to a= scheduled plant shutdown, the reactor (primary)
L
- coolant system was chemically shocked to induce.a crud burst.
What-effect will this have on the letdown purification demineralizers?
- A.
Increased flow-rate through the demineralizers
,.o <
p<,.
B.
'Demineralizers will become boron saturated H 6h 2
llc C.-
Decreased demineralizer outlet conductivity D.
' Increased pressure drop across the demineralizers FORM B 42 l
\\
O.
QUESTION:
93-A domineralizar is BORON SATURATED when the domineralizer:
A.
effluent contains a: higher boron concentration than the
'demineralizer influent.
B.
absorbs greater than 20 ppm boron per hour.
C.
influent and effluent boron concentrations-are equal.
D.
effluent boron concentration rapidly increases.
QUESTION:
94 1
To deenergize-a component and its associated control and indication circuits, the component circuit' breaker should be:
A.
open;with' control power fuses removed.
4 B.
racked in;with control power fuses removed._
i" C.
rackediout and tagged in racked-out position.
D.
racked out with control power fuses removed.
J i
-l I
.l 1
FORM B 43 i
- )
~. -
QUESTION:
-95 The 'following remote indications are observed for a 480 VAC load
]
supply breaker.
Red indicating light is on.
Green indicating-light is off.
Load voltage indicates 0 volts.
Line voltage indicates 480; volts.
What is the condition of the breaker?
A.
Open and racked in B.
Closed and racked in
,.C.
Open and racked to " test" position
-D.'
Closed and racked to " test" position L
QUESTION:
96 L
Loss of, breaker control power will:
A.
remove all local indication of breaker position.
B.
prevent local tripping of the' breaker.
l C.
remove the breaker tripping function on remote interlock.
D.
prevent 1the breaker from tripping on overcurrent.-
p t-a FORM B 44 I:
l
e v.
-o d,
1 I
QUESTION:
97 During paralleling operations of the main generator to the grid, closing.the generator output breaker with the frequency of the generator at.60.1 hertz and the grid frequency at 60.0 hertz will:
A.
cause the generator to immediately increase load.
B.
trip open the generator breaker on reverse power.
C.
cause the generator voltage to increase.
D.
cause the generator current to decrease, j
1 QUESTION:
98-l-
l-Which of the following describes the BEST method for completely deenergizing a breaker control circuit?
-A.
Breaker in test position.
'B.
Breaker' fully racked'out.
C.
Control' power fuses removed.
D.
Control switch in pull-to-lock.
[
g
. QUESTION:
99 The function of high. voltage electrical disconnects is to provide electrical. isolation of equipment during-
- j conditions.
u A.
manual; no-load-B..
manual; overload s
C.-
automatic; no-load 1-f D.
automatic; overload i
i FORM B 45
.m..
m -
, - - - - -