ML20203D238
| ML20203D238 | |
| Person / Time | |
|---|---|
| Issue date: | 12/03/1997 |
| From: | Spessard R NRC (Affiliation Not Assigned) |
| To: | Linnen D INSTITUTE OF NUCLEAR POWER OPERATIONS |
| References | |
| NUDOCS 9712160142 | |
| Download: ML20203D238 (148) | |
Text
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j NUCLEAR REGULATORY COMMISSION
- I WASHINGTON, D.C. 30646 0001
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December 3, 1997 Mr. David C. Linnen. Manager-Training Activities Department Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta Georgia 30339-5957
Dear Mr. Li;,
nen:
The October 8, 1997. Generic Fundamentals Examination (GFE) was administered to 173 candidates at 28 facilities. The examination operated smoothly and without incident.
The summary statistical results of this exam are as follows:
BWR PWR Candidates 84 89 Mean score 90.51
')1. 44 High score 98 100 Low score 70 73 No of failures 5
1 Failures by plant 79 Quad Cities 73 Byron 78 Nine Mile Point One 77 Cooper 76 WNP-2 70 Duane Arnold The statistical results of this exam, e.g,. mean st. ores and range are generally in line and stable with past exam performance. Overall exam difficulty level (i.e.. mean score) is targeted at 87.00 and actual
'7 'h*
exa.9 difficulty levels of 90 and 91 are sufficiently close to targeted goals and con ^1 stent with past GFE performance. As in p evious exams since February 1992, this exam was developed using the merged INP0/NRC test bank from your catalogs.
Overall we believe this exam was a good product and a i
valid measure of generic fundamental knowledge.
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D. Linnen Eneility Cn=mants and Answer Key Chanaes There were no PWR facility comments received for this examination and only t's BWR facilities made comments.
Regarding the two BWR facility comments, we reviewed and researched each of the comments affecting the two items.
Based upon our analysis, we revised the grading of one item to be adjusted to accept two correct answers, but no answer key change was made to the other item.
Question f Change BWR item #85 Accept two answers. C or D BWR item #35 No change The above BWR item #85, containing two correct answers will be deleted from the NRC examination bank. Accordingly, this item has also been deleted from the BWR hard copy and computer diskette enclosures to this letter so as not to be entered into the BWR examination catalog bank in your annual catalog updates.
As we have routinely done, we are enclosing both BWR and PWR hard copws of the exam (fnclosures 1 and 2. respectively) as well as a floppy diskette (Enclosure 3) which contains the contents of this examination along with its associated catalog input data needed for updating your catalogs.
If you have any questions, please contact George M. Usova at (301) 415-1064.
Sincerely.
YbN R. Lee Spessard, Director Division of Reactor Controls and Human Factors Office of Nuclear Reactor Regulation
Enclosures:
As stated
D. Linnen 2
December 3,1997 i.
Encility Crnts and Answer Key Chanoes 1
There were no PWR facility comments received for this examination and only two BWR facilities made comments.
Regarding the two BWR facility comments, we reviewed and researched each of the comments affecting the two items.
Based upon our analysis, we revised the grading o'f one item to be adjusted to accept two correct answers, but no answer key change was made to the other item.
Question #
Change BWR item #85 Accept two answers. C or 0 BWRitem#35 No change The above BWR item #85. containing two correct answers will be deleted from the NRC examination bank. Accordingly, this item has also been deleted from the BWR hard copy and computer diskette enclosures to this letter so as not to be entered into the BWR examination catalog bank in your annual catalog updates.
As we have routinely done, we are enclosing both BWR end PWR hard copies of the exam (Enclosures 1 and 2. respectively) as well as a floppy diskette (Enclosure 3) which contains the contents of this examination along with its associated catalog input data needed for updating your catalogs.
If you have any questions, please contact George M. Usova at (301) 415-1064.
Sincerely.
Original signed by:
Jared S. Wermiel (for)
R. Lee Spessard Director Division of Reactor Controls and Human Factors Office of Nuclear Reactor Regulation
Enclosures:
. As stated DISTRIBUTION:
Central Files PUBLIC GUsova w/o encls:
HOLB r/f RGallo LSpessard
- See previous concurrence DOCUMENT NAME: G:\\USOVA\\INPOCT97 e t it To voceive eco py of this document, Indicato in the bos: *C's Copy without attachment /endoeure *E's Copy with attachment /endosure '90 = No cxmy omCE HOLILDRCH I
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UNITED STATES NUCLEAR REGULATORY CONNICSION BOILING WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 - FORM A
+
September 17, 1997 Please Print Hame:
Facility:
L Docket No.:
Start Time:
Stop Time:
INSTP.UCTIONS TO APPLICANT Answer all the test items using the answer sheet provided.
Each item has equal point value.
A score of at least 80% is required to pass this portion of the written licensing examination.
All examination papers will be collected 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> after the examination starts.
This examination applies to a typical boiling water reactor (BWR) power plant.
SECTION QUESTIONS
% OF TOTAL SCORE COMPONENTS 1 - 44 REACTOR TilEORY 45 - 72 THERMODYNAMICS 73 - 100 TOTALS 100 All work done on this examination is my own.
I have neither given nor received aid.
Applicant's Signature,
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RULES AND GUIDELINES FOR TME G m oM j
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.
t i
2.
Fill in the name-of your facility.
3.
Fill in your individual docket number.
4.
Fill in your start and stop times at the appropriate titae.
5.
Two aids are provided for your use during the examination:
(1)
An equations and conversions sheet contained within the examination copy, and 4
(2)
Steam tables provided by your proctor.
6.
Place your answers on the 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 papor will be provided for calculations.
8.
Cheating on the examination will result in the automatic forfeiture of this examination.
Cheating could also result in severe penalties.
9.
Restroom trips are limited.
Only ONE examinee may leave the room at a time.
In order to avoid the appearance or possibility of cheating, avoid all contact with anyone outside of the examination rocm.
10.
After you have completed the examination, sign the statement on the cover sheet indicating that the work is your own and you have not received or been given any assistance in completing the examination.
11.
Turn in your examination materials, answer sheet on top, followed by the examination booklet, then examination aids -
steam table booklets, handouts and scrap paper used during the 4
examination.
12.
After turning in your examination materials, leave the examination area, as defined by the proctor.
If after leaving you are found in the' examination area while the examination is in progress, your examination may be forfeited.
1 -
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i GENERIC FUNDAMENTALS EXAMINATION t
EQUATIONS AND CONVERSIONS MANDOUT SHEET EQUATIONS l
Q = rhC 6T P = P.108* 8" p
Q = rhah P = P e
'd lt Q = UA6T A = A,e-At h " th'et Circ
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CR (1 - Kerrt) = CR (1 - Kerra) 3 1/M = CR /CR, 3
- Fwer = 1/ (1 - P)
DRW - 9'i,/<p',
p= (Kerr - 1) /K.f r
^
SUR = 26.06/t rh = pAV
,,0-p Aerr P ba
= rhaPu E = IR p. _c_-
Ti t
I + A,,gt Eff. = Net Work Out/ Energy In ga) + g(22 f* = 1 x 10** seconds U(P -P) + (g 2) 0
=
2 2
U" A.es = 0.1 seconds 2 32.2 lbm-ft/lbf-sec8 ge =
CONVERSIONS
-~~-~~~~.-~~~------__...-__--__....___............_________ __ ____
3.41 x 10' Btu /hr 1 Curie l
1 Mw
=
3.7 x 10' dps 2
c 2.54 x 102 i hp Bto/hr 1 kg
=
2.21 lbm
=
i Btu =
778 ft-lbf 1 gal.., =
8.35 lbm
- C (5/9) ("F - 32) 1 f t' 7.48 gal
=
=
l
- F (9/5) (*C) + 32
=
l l
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i USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BNR - FORN A
\\
i- *-
QUESTION:
1 TOPIC:
291001 KNOWLEDGE:
K1.01 QID:
B1701 A vertical safety valve has a compressed spring assembly that is applying 1200 lbf to the top of the valve disk in opposition to system pressure.
System pressure is being exerted on the underside of the valve disk that is 3 inches in diameter.
Which one of the following is the approximate system pressure at which the safety valve will open?
(Neglect the effect of atmospheric pressure.)
A.
44 psi B.
64 psi c
C.
128 psi D.
170 psi ANSWER:
D.
-PROOF:
F = PA P = F/A P = 1200/3.14 (1.5):
P = 1200/7.07 P = 169.7 psi QUESTION:
2 TOPIC:
291001 KNOWLEDGE:
Kl.04 QID:
B1702 Which one of the following statements describes the flow rate characteristics of a typical gate or globe valve?
A.
The last 25% of valve stem movement in the open direction for a gate valve will produce a greater change in flow rate than the first 25% of valve stem movement.
B.
The last 25% of valve stem movement in the open direction for a 3
globe valve will produce a greater change in flow rate than the first 25% of valve stem movement.
C.
A globe valve designed specifically for throttling flow must be operated in the first 25% of its range to control flow.
D.
The first 25% of valve stem movement in the open direction for a gate valve will produce a greater change in flow rate than the last 25% of valve stem movement.
ANSWER:
D. -
USMRC GENERIC FUNDAMENTALS REAttIMATION OCTOBER 1997 BWR - FORM A QUESTION:
3 TOPIC:
291001 KNOWLEDGE:
K1.05 QID:
B1404 Which one of the following is a generally accepted method for locally verifying.that a manual valve is fully closed in a depressurized static piping system?
A.. Check a downstream flow gauge to be indicating zero flow B.
Visually observe the valve rising-stem threading to be fully exposed C.
Attempt to' turn the valve handwheel in the close direction and verify no movement D.
Compare an upstream and downstream pressure gauge to ensure-zero differential pressure ANSWER:
C.
QUESTION:
4 TOPIC:
291001 KNOWLEDGE:
Kl.07 QID:
B1102 (Rev)
Two common types of check valves used in power plants are:
A.
globe and gate.
B.
ball.and plug.
C.
swing and lift.
E.
needle and angle.
ANSWER:
C..
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i USNRC GENERIC FUNDMEWITALS EXAMINATION l
OCTCCER 1997 BWR - FORN A QUESTION:
5 TOPIC:
291001 KNOWLEDGE:
K1.02 QID:
B2005 (Rev)
When comparing the characteristics of gate valves and globe valves in an operating system, a globe valve generally has a pressure drop when fully open, and is commonly used for throttling system flow.
A.
smaller; less B.
larger; more C.
smaller; more D.
larger; less ANSWER:
B.
d QUESTION:
6 TOPIC:
291002 KNOWLEDGE:
K1.01 QID:
B706 (Rev) 1 A cooling water system is operating at a steady-state flow rate of 700 gpm with 60 paid across the flow transmitter venturi.
If-cooling water flow rate is increased to 900 gpm, differential pressure across the flow transmitter venturi will be:
l A.
68.0 psid.
B.
77.1 psid.
C.
99.2 psid..
D..
127.5 psid.
ANSWER:
C.
PROOF:
8 D/P = F D/P =-D/P (F /F )2 t
2 3
= 60 (900/700)'
= 99.2 -
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US30tC GENERIC FUNDAMENTALS EXAMINATIOtt OCTOBER 1997 BWR - FORM A 1
QUESTION:
7 TOPIC:
291002 KNOWLEDGE:
Kl.04 QID:
B707 Which one of the following will cause indicated flow rate to be A hg than actual f3ow rate using a differential pressure flow h
detector and a calibrated orifice?
A.
Debris becomes lodged in the orifice.
~
B.
A leak develops in the high pressure sensing line.
C.
The orifice erodes over time.
I D.
The flow detector equalizing valve is inadvertently opened.
ANSWER:
A.
4 6
QUESTION:
8 TOPIC:
291002 KNOWLEDGE:
Kl.12 QID:
B611 Which one of the following parameters requires square root extraction when measured by differential pressure detectors?
i A.
Condenser vacuum B.
' Reactor vessel level C.
Reactor vessel pressure D.
Recirculation pump flow rate ANSWER:
D.
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USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:
9 TOPIC:
291002 KNOWLEDGE:
Kl.05 i
QID:
B1808 (Rev) j Refer to the drawing of a pipe elbow used for flow measure'. ent in a cooling water system (see figure below).
A differential pressure (D/P) flow detector is connected to instrument lines A and B.
If instrument line A develops a leak, indicated flow rate wi:1 due to a measured D/P.
A.
increase; larger B.
increase; smaller C.
decrease; larger D.
decrease; smaller ANSWER:
D.
fit J
6=
A PIPE EL80W
USMRC GE8MRIC FUNDhMENTALS EXAMINATION OCTOBER 1997 BWR - FORN A
)
QUESTION:
10 TOPIC:
291002 KNOWLEDGE:
Kl.08
)
QID:
B1909 (Rev)
Refer to the drawing of a tank differentiel pressure (D/P) level detector (see figure below).
The level detector is being used in a level control system that is calibrated to maintain tank level at 80% at the current water temperature of 70*F.
If water temperature gradually increases and stabilizes at 90*F, the level control system will cause actual tank' level to:
A.
remain at 80%.
B.
increase and stabilize above 80%.
C.
oscillate around 80%.
D.
decrease and stabilize below 80%.
ANSWER:
B.
O T PH3RE WATEM s
Y DIP DETECTOR r
TANK DIFFERENTIAL PRESSURE LEVEL DETECTOR 9-
USMRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A I
QUESTION:
11 TOPIC:
291002 KNOWLEDGE:
K1.08 QID:
-NEW Refer to the drawing of a tank with a differential pressure level detector (See figure below.).
The. level detector was calibrated with reference leg and tank contents temperature at 70*F.
An increase in ambient temperature causes the temperature of the reference leg and tank contents to increase to 110*F.
With the temperature of the reference leg and tank content.s stable at 110*F, current level indication will be A.
higher than initial due to reference leg spill over.
B.
higher than initial due to expansion of tank contents.
C.
the same as initial due to offsetting density changes in the reference leg and tank contents.
D.
the same as initial due to the reference leg being connected to the upper portion of the tank.
ANSWER:
A.
REFERENCE LEG FILL CONNECTION M
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GAS OR VAPOR d
PRESSURE S
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h EQUAll21NG h
VALVE
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/
za DETECTOR I.
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TANK OlFFERENTIAL PRESSURE LEVEL DETECTOR --
USNRC GENERIC FUNDAMENTALS EXAMINATIOtt OCTOBER 1997 BNR - FORN A 4
QUESTION:
12 TOPIC:
291002 YWOWLEDGE ' K1.19 QID:
B1214 The reactor scrammed due to a loss-of-coolant accident i hour ago.
To verify adoquate reactor vessel water level, the source range monitors (SRMs) are inserted.
As the SRMs enter the core, count i
rate begins to increase and then stabilizes.
If the SRMs enter a voided section of the core, count rate will l
suddenly:
A.
decrease due to decreased fast fission.
B.
decrease due to increased neutron leakage.
C.
increase due to increased neutron migration length.
D.
increase due to decreased moderator neutron absorption.
I ANSWER: B.
QUESTION:
13 TOPIC:
291002 KNOWLEDGE:
K1.24 QID:
NEW An initial radiation survey is about to be performed in an area of unknown radiation field intensity.
Which one of the following types of radiation monitoring instruments and settings should be used?
A.
A Geiger Mueller survey meter selected to the low range B.
A Geiger Mueller survey meter selected to the high range C.
An ion chamber survey meter selected to the low range D.
An ion chamber survey meter selected to the high ranga ANSWER: D.
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USNRC GENERIC FUNDMEENTALS EXAMINATION OCTOCER 1997 BWR'- FORM A QUESTION:
14 i
TOPIC:
291002 KNOWLEDGE:
K1.21 QID:
B2114 A gas-filled radiation detector operating in the proportional region is exposed to a constant gamma radiation field.
If the i
applied voltage is increased but maintained within the proportional region, the rate of ion collection will:
A.
stay approximately the same because all of the primary ions were already being collected at the lower voltage.
B.
stay approximately the same because the detector is operating at saturated conditions.
C.
increase because fewer primary ions are recombining in the detector prior to reaching the electrodes.
D.
increase because more st.condary ionizations are occurring in the detector.
ANSWER:
D.
QUESTION:
15 i
TOPIC:
291003 KNOWLEDGE:
K1.03 OID:
B1317 (Rev)
Which one of the following controller types is designed to control the measured parameter at the controller set point?
A.
Integral
- B.
Proportional C.
On-Off D.
Derivative ANSWER:
A.
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USMRC amantELIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A
]
QUESTION:
16 TOPIC:
291003 KNOWLEDGE:
K1.05 QID:
B1416 (Rev)
Which one of the following describes a characteristic of pneumatic valve positioners?
A.
They can provido auto and manual demand signals to valve controllers and valve actuators.
B.
They can automatically increase or decrease air pressure to valve act"ators to overcome sluggish valve response.
C.
They can either receive or supply air to/from valve controllers, depending on the direction of valve travel.
D.
They can increase air pressure to valve actuators above existing main air header pressure.
ANSWER:
B.
i QUESTION:
17 TOPIC:
291003 KNOWLEDGE:
Kl.06 QID:
B1815 A diesel generator is supplying a bus with the governor operating in the isochronous mode.
If a large electrical load is started on the generator bus, generator frequency will:
A.
remain constant during and after load start, t
B.
initially decrease and then increase and stabilize below the initial value.
C.
laitially decrease and then increase and stabilize at the initial value.
D.
-initially decrease and then increase and stabilize above the initial value.
ANSWER: C.
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US8Dtc GENERIC FUMn& MENTAL 5 EXAMINATION I
OCTOBER 1997 BWR - FORM A l
QUESTION:
18
)
TOPIC:
291004 KNOWLEDGE:
K1.01 QID:
B1718 Starting a centrifugal pump with the discharge valve throttled (versus fully open) the possibility of pump runout and the possibility of pump cavitation.
3 A.
increases; decreases B.
increases; increases C.
decreases; decreases D.
decreases; increases ANSWER:
C.
QUESTION:
19 TOPIC:
291004 KNOWLEDGE:
K1.07 QID:
B419 (Rev)
A centrifugal pump is circulating water at 150*F in a cooling water system.
After several hours the water temperature has decreased to 100*F.
Assuming system flow rate (gpm) is constant, pump motor amps will have because has increased.
A.
increased; water density B.
increased; motor efficiency C.
decreased; water density D.
decreased; motor efficiency ANSWER: A...
x
. _ _ - _ ~ _ _ - -
USalRC GE3fERIC FUBEDAMEllTALS EXAMIFO'"Ott OCTOBER 1997 EWR - FORM A QUESTION:
20 TOPIC:
291004 KNOWLEDGE:
Kl.06 QID:
B1918 Refer to the drawing of a cooling water system (see figure below).
The available net positive suction head for the centrifugal pump will be decreased by:
A.
opening surge tank makeup valve "A" to raise tank level.
B.
throttling heat exchanger cooling water valve "B" more open.
C.
throttling pump discharge valve "C" more open.
D.
redue mg the heat loads on the cooling water system.
ANSWER:
C.
A guaa
- 9;
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PUMP COOLING WATER SYSTEM 15 -
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USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:
21 TOPIC:
291004 KNOWLEDGE:
K1.13/K1.19 QID:
B1725 Two identical centrifugal pumps (cps) and two identical positive displacement pumps (PDPs) are able to take suction on a vented water storage tank and provide makeup water flow to a cooling water sys:em.. The pumps are capable of being cross-connected to provide multiple configurations.
In single pump alignment, each pump will supply 100 gpm at a system pressure of 1000 psig.
Given the following information:
J Centrifugal Pumps j
Shutoff head:
1500 psig Maximum design pressure:
2000 psig Positive Displacement Pumps Maximum design pressure:
2000 psig Which one of the following pump configurations will supply the lowest makeup flow rate to the system if system pressure is at 1700 psig?
A.
Two cps in parallel j
B.
Two cps in neries C.
One PDP and one CP in parallel D.
One PDP and one CP in series (CP supplying PDP)
ANSWER: A.
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i USNRC GENERIC FUNDAMENTALS EXANINATION OCTOBER 1997 BNR - FORN A t
- QUESTION:
22 TOPIC:
291004 KNOWLEDGE:
Kl.ll QID:
B925 Refer to the drawing of a centrifugal pump operating curve (see figure below).
Which one of the following determines the general shape of the curve from point D to point B7 A.
Pump flow losses due to the decrease in available net positive '
suction head as the systeem flow rate increases B.
Pump flow losses due to.back leakage through the clearances
-between the pump impeller and casing as the D/P across the pump incr~ases C.
The frictional and throttling losses in the piping system as the system flow rate increases D.
The frictional losses between the pump impeller and its casing as the differential pressure (D/P) across the pump increases i
ANSWER:
C.
POINT A
/
PUMP POINT B HEAD I
- POINT D POINT C
/
/
F FLOW i
CENTRIFUGAL PUMP OPERATING CURVE l
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USNRC GENERIC FUNDMEENTALS LXAMINATION OCTOBEM 1997 BWR - FORM A QUESTION:
23 TOPIC:
291004 KNOWLEDGE:
Kl.06 OID:
Bil20 (Rev)
A motor-driven centrifugal pump is operating in an open system.
If the pump discharge valve is fully opened from a throttled position, available net positive suction head (NPSH) will and required NPSH will 5
A.
increase; increase B.
increases remain the same C.
decrease; increase D.
decrease; remain the same ANSWER:
C.
P QUESTION:
24 TOPIC:
291004 KNOWLEDGE:
Kl.18 QID:
B1125 Which one of the following describes the proper location for a relief valve that will be used to prevent exceeding the design pressure of a positive displacement pump and associated piping?
A.
On the pump discharge piping upstream of the discharge isolation valve B.
On the pump discharge piping downstream of the discharge isolation valve C.
.On the pump suction piping upstream of the suction isolation valve D.
On the pump suctJ.on piping downstream of the suction isolation valve ANSWER:
A.
4
+ _
USIOtc GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORN A 4
QUESTION:
25 TOPIC:
291004 KNOWLEDGE:
Kl.04 OID:
B1219 (Rev)
Refer to the drawing of a pump with a recirculation line (see figure below).
Valve "A" will close when pump:
A.
discharge pressure reaches a high set point.
B.
discharge pressure reaches a low set point.
C.
flow rate reaches a high set point.
D.
flow rate reaches a low set point.
I ANSWER: C.
A VALVE
.:. ORIFICE
]
h.
DISCHARGE r
SUCTION PUMP PUMP WITH RECIRCULATION LINE.
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 SWR - FORM A
-QUESTION:
26 TOPIC:
291005 KNOWLEDGE:- Kl.01 QID -
B1026 A motor-driven centrifugal pump exhibited indications of pump failure while being started.
Which one of the following pairs of indications will-occur if the pump failure is a sheared impeller shaft?
A.
Excessive duration of high_ starting current and motor breaker trips B.
Excessive duration of high starting current and no change-in system flow rate C.
Lower-than normal running current and motor breaker trips D.
Lower than normal running current and no change in system flow rate ANSWER:
D.
QUESTION:
27 TOPIC:
291005 KNOWLEDGE:
Kl.05 QID:
NEW Two identical 4160 Vac induction motors are connectd to identical centrifugal pumps being used to provide cooling water flow in separate systems in a power plant.
Each motor is rated at 1000 hp.
The discharge valve for pump A is fully'open and the discharge valve for pump B is fully shut.
If each motor is then started, the longest time period required to stabilize motor current will be experienced by motor and the higher stable motor current will be experienced by motor A,
A; A B.
A; B C.
B; A D.
B; B ANSWER:
A.
L l -.
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r USNRC GENERIC W M ALS EXAMINATION OCTOBER 1997 BWR - FORN A QUESTION:
28 TOPIC:
291005 KNOWLEDGE:
K1.03 QID:
NEW If the voltage supplied by an ac generator to an isolated electrical system is held constant i, f real load (kW) is i
increased, the current rupplied i,
-,e
'onerator will increase.in direct proportion to the
>t the change in real load.
(Assume power factor does not cha.;;e A.
square root B.
amount C.
square D.
cube ANSWER:
B.
QUESTION:
29 TOPIC:
291005 KNOWLEDGE:
K1.04 QID:
B326 (Rev)
A centrifugal pump is operating at 600 rpm with the following parameters:
Motor' current
= 100 an, peres Pump head
= 50 psid Pump flow rate = 880 gpm Which one of the following will be the approximate value of pump head if pump speed is increased to 1200 rpm?
A.
71 psid B.
100 psid C.
.141 psid D.
200 psid ANSWER:
D.
m..._ _ _. _ _ _ _ -.
USNRC GEllRRIC FUIEWERIFFALS EXAMINATIOOf OCTOBER 1997 BWR - FORM A PROOF:
H /H (S /S,) 2 j
=
3 3
3 a H + (S /S )8 Ha 3
3 50 + 0.25 H =
3 i
200 paid l
H2
=
1 I
1 i
i 4
?
I
(
e--,
, - - ~.. _. -. -
wi,.
USNRC n N IC FUNDAMENTALS EXAMINATION 1
OCTOBER 1997 BNR - FORM A QUESTION:
30 TOPIC:
291005 KNOWLEDGE:
Kl.08 QID:
B729 The main generator is operating on the grid with the following indications:
)
100 MWe 100 MVAR (VARs out) 2,800 amps If main generator excitation is increased slightly, amps will and MWe will A.
decrease; increase B.
decrease; remain the same C.
increane; increase D.
incree.se; remain the same ANSWER:
D.
QUESTION:
31 TOPIC:
291006 KNOWLEDGE:
K1.03 QID:
B631 The rate of heat transfer between two liquids in a heat exchanger will be increased if the:
(Assume single-phase conditions and a constant specific heat capacity.)
A.
flow rate of the colder liquid is decreased by 10%.
B.
flow rate of the hotter liquid is increased by 10%.
C.
temperature of both liquids is decreased by 20*F.
D.
temperature of both liquids is increased by 20*F.
ANSWER:
B.
f
..... - - ~
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BNR - FORM A QUESTION:
32 TOPIC:
291006 KNOWLEDGE:
K1.07 QID:
B1231 Refer to the drawing of a water cleanup system (see figure below).
All valves are identical and are initially 50% open.
To lower the temperature at point 4, the operator should e.djust valve in the direction.
A.
A; open B.
B; shut C.
C; open D.
D; shut ANSWER:
Bs R m RN FROM SY EM SYSTEM o
540*FI'2 1
A HEAT EXCHANGER 122*F C
250*F 1 !4 5
HEAT 9h*F EXCHANGER COOLING 6
WATER 110*F 122*F ii7 ION EXCHANGER WATER CLEANUP SYSTEM 24 -
A
(
l*
USNRC GENERIC FUNDAMENTALS EXAMLEATION OCTOZER 1997 BWR - FORN A QUESTION:
33 TOPIC:
291006 KNOWLEDGE: -Kl.08 QID:
B2132 (Rev)
Refer to the drawing of a lube oil heat exchanger (see figure below).
The lube' oil heat exchanger is in service with the following inlet temperatures:
Lube oil inlet temperature:
130*F Cooling water inlet temperature:
70*F Assuming cooling water flow rate is greater than lube oil flow rate, which one of the following sets of heat exchanger outlet temperatures is possible?
( Assume both fluids have the same c,. )
Lube Oil Cooling Water Outlet Temp Outlet Temp A.
90*F.
100*F B.
90*F 110*F C.
100*F 100*F D.
100*F 110*F ANSWER:
A.
$llI!! h*'.l'"... ' fll,Il 5; f j;.
i h;.
- g' - " '
.A.11 h:1
..a.
=
m A3 k
_=,v, i
LUS$ OtL LUBE Olt HEAT EXCHANGER
..... _ - ~..._. -. - _ - ~ - -. _.
USEDtc GENERIC-FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A.
l PROOF:
A.
is-the only option that shows a cooling water temp. increase that is smaller than the lube oil temp. decrease.
This must be the case since cooling water. flow rate is greater than lube oil flow rate.
i 4
S l
- 2e -
4
..-a.<,,
o e
i Usamc GENERIC FUNDMEENTALS EXAMINATION.
OCTOBER-1997 BWR FORM A-QUESTION:- TOPIC:.
291006 KNOWLEDGE:
K1.13 QID:
B1536 Which one of the following describes the' state of water at 160'psig and 366*F?.
A.
Saturated liquid B.
Subcooled liquid
- C.
Superheated vapor
- D.
Mixture of saturated liquid and vapor ANSWER:
B.
PROOF:
P..
for 366*F is - 165 psia P,e., is 160 psig + 15 = 175 psia P.t.r
> P..t = subcooled w
= QUESTION:
35 TOPIC:
291006 KNOWLEDGE:
Kl.18
. QID:-
'B334 (Rev) 4
'A plant is operating at 100% power when air inleakage results in the buildup of noncondensible gases in the main condenser.
Which one of the following will occur as a result of this air inleakage?
A.
Decreased condensate temperature B.
Decreased' pressure in the main condenser
- C.
Decreased suction pressure at the condensate pumps D.
Decreased condenser cooling water outlet temperature f
ANSWER:
D. ;
USNRC GENERIC FUNDAIGNTALS EXAMINATION OCTOBER 1997 BWR - FORN A QUESTION:
36 TOPIC:
291006 KNOWLEDGE:
K1.16 QID:
B1234 Refer to the drawing of a lube oil heat exchanger (see figure below).
If scaling occurs inside the cooling water tubes, cooling water outlet temperature will and lube oil outlet temperature will (Assume oil and cooling water flow rates remain the same.)
A.
decrease; decrease B.
decrease; increase C.
increase; decrease D.
increase; increase ANSWER:
B.
w w
-ll 5 5)i,M,:I WATER JERES LUGE OR.
LUBE Ott HEAT EXCHANGER USNRC GENERIC FUNDAMEF1'ALS EXAMINATION OCTOBER 1997 BNR - FORM A QUESTION:-
- 37 TOPIC
'291007 KNOWLEDGE:
Kl.05 QID:
B337 (Rev)-
f How does_demineralizer differential pressure. indicate the condition of the demineralizer resin bed?
A.
Low differential pressure indicates flow blockage in the demineralizer.
i
~
B.
Low differential _ pressure indicates thac the demineralizer resin bed is exhausted.
C.
High differential pressure indicates flow blockage in the demineralizer.
D.
High differential pressure indicates that the demineralizer resin bed is e:dausted.
ANSWER:
C.
QUESTION:
38 TOPIC:
291007 KNOWLEDGE:
Kl.07 QID:
_B39 (Rev)
When a mixed-bed demineralizer cesin is exhausted, the resin should be replaced or regenerated because:
A.
ions previously removed by the resin will be released into solution.
B.
the resin will fracture and possibly escape through the retention screens.
C.
particles previously filtered out of solution will be released.
D.
the resin will physically bond together, thereby causing a flow blockage.
ANSWER:
A.
I i
L
_ ~.
USNRC-GENERIC. FtprmNALJ EXAMINATION OCTOBER 1997 BNR - FORM A
- QUESTION:
39 TOPIC:
291007
. KNOWLEDGE:
K1.07 QID:
B1039.
The anion resin in a mixed-bed demineralizer releases ions.into solution while removing charged ions from solution.
A.
hydroxide;' negetively B.-
hydroxide; positively C.
hydresen; negatively D.
hydrogen; positively
. ANSWER:
A.
i QUESTION:
40 TOPIC:
291008 KNOWLEDGE:
K1.02 QID:
B1144 (Rev)
Circuit breaker local overcurrent trip flag indicators, when actuated, indicate that:
A.
c breaker trip will occur unless current is reduced.
B.
a breaker overcurrent condition is responsible for a breaker trip.
C.
an overcurrent condition has cleared and the breaker can be closed.
D.
the associated-circuit breaker has failed to trip open during an overcurrent condition.
ANSWER:
B.
1 - -
i USNRC GENERIC FUNDADENTALS EXAMINATION OCTOCER 1997 BWR - FORM A
-QUESTION:~
41 TOPIC:
291008 KNOWLEDGE:
K1.03 OID:
B1044
.Which one of the following describes a benefit of using charged springs (in lieu of a closing coil or solenoid operator) to close some large motor breakers?
A.
Springs produce faster breaker closing.
B.
Springs can be repaired or replaced without removing the breaker from service.
C.
Springs provide stored energy to allow local cycling of the breaker upon loss of control power.
D, Springs will keep the breaker contacts firmly seated after closing to minimize arcing and prevent inadvertent opening.
ANSWER:
C.
QUESTION:
42 TOPIC:
291008 KNOWLEDGE:
K1.05 QID:
B1041 (Rev)
Thermal overload devices will provide the first motor protection in the event of a/an:
A.
locked rotor.
B.
electrical short circuit.
C.
gradual motor bearing _ damage.
D.
sheared shaft.
ANSWER:
C.
, i
.~
USNRC GENERIC FUNDANENTALS EXAMINATION OCTOCER 1997.BWR
. FORM A QUESTION:
43
- TOPIC:-
-291008 KNOWLEDGE:
Kl.08 QID:
B1143 A three-phase ac generator is being paralleled to the grid with the following conditions:
Generator frequency: 59.5 Hz Grid frequency:
59.8 Hz Generator voltage:
115.1 kV Grid voltage:
114.8 kV When the generator. output breaker is closed the generator will:
A.
acquire real load and reactive load.
B.
acquire real load and-become a reactive load to the grid.
C.
become a real load to the grid and acquire reactive-load.
D.
become a real load and a reactive load to the grid.
ANSWER:
C.
Y QUESTION:
44 TOPIC:
291008 KNOWLEDGE:
K1.10 QID:
B1544 (Rev)
What is an advantage of using high voltage electrical disconnects inttead of breakers to isolate main power transformers?
A.
Disconnects provide positive visual indication that the circuit is broken.
B.
Disconnects can be operated either locally or remotely.
C.
Disconnects are cheaper and provide the same automatic protection as a breaker.
D.
Disconnects are capable of passing a higher current with less heating than a breaker.
ANSWERt A.
USNRC GENERIC FtPmunTALA EXAMINATION OCTOBER 1997 BWR - FORM A
. QUESTION:
45
-TOPIC:
292001 KNOWLEDGE:
K1.02 QID:
B1445 (Rev)
As compared to a prompt neutron, a delayed neutron, born from the same fission event, is more likely to:
A.
leak out of the core.
B.
be absorbed in a B-10 nucleus.
C.
undergo resonance capture in a Pu-240 nucleua.
D.
cause fission of a U-238 nucleus.
ANSWER:
B.
QUESTION:
46 TOPIC:
292001
. KNOWLEDGE:
K1.03 QID:
B945 Regarding a thermal neutron, the word " thermal" indicates that the neutron:
A.
was born greater than 10'" seconds af ter the fission event.
B.
is a product of a thermal fission reaction.
C, was released by the decay of fission fragments.
D.
is at the same energy level as the surrounding atoms.
ANSWER:
D. _
-USNRC GENERIC FUNDMENTAL3 EXAMINATION OCTOBER 1997-CNR - FORN A QUESTION:
47 TOPIC:
292002 KNOWLEDGE:
Kl.09 QID:
B1147
~The following are combinations of critical conditions that exist
- for the same reactor operating at 20% power at different times in core life.
Which one of the following combinations indicates the
- largest amount of excess reactivity exists in the core?
CONTROL ROD REACTOR RECIR-POSITION CULATION FLOW-A.
25% rod density 25%
B.
25% rod density 50%
C.
50% rod density 25%
~
D.
-50% rod density 50%
ANSWER: C.
QU2STION:
48 TOPIC:
292002 KNOWLEDGE:
K1.14 QID:
-B1748 (Rev)
Sixteen hours ago, a reactor scrammed from 100% steady state power due to an instrument raalfunction.
All systems operated normally.
Given the following absolute values of reactivities added since the scram, assign a (+) or (-) as appropriate and choose the current 4
value of core reactivity.
( ) 2.0% AK/K Xenon
=
Fuel temperature = ( ) 3.0% AK/K Control rods
( ) 12.0% AK/K
=
Voids
( ) 4.0% AK/K.
=
A.
-5.0% AK/K B.
-7.0% AK/K
- C.
-9.0% AK/K D.
-11.0% AK/K ANSWER:
B.
PROOF:
-2
+3.0
-12
+4.0
-14
+7.0 -.= - -
USNRC QENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A-QUESTION:
49 TOPIC:
292003 KNOWLEDGE:
K1.01 QID:
NEW Two. reactors are currently shut down-with a reactor startup in
. progress. The two reactors are identical _except that reactor A has a source neutron Ptrength of 100 neutrons per second and reactor B rource neutron strength is 200 neutrons per recond. Control rods are stationary land Keff is 0.98 in both reactors.
Core neutron level has reached equilibrium in both reactors.
Which one of the following lists the core neutron level (neutrons per second) in reactors A and B?
Reactor A Reactor B A.
5,000 10,000 B.
10,000 20,000 C.
10,000 40,000 D.
20,000 40,000 ANSWER:
A.
PROOF:
4 i
)
.CRsfo = S/(1-K)
Reactor A CRs,o = 100/.02
= 5,000 Reactor B CRsio = 200/.02
= 10,000 _
USNRC GENERIC FUNDMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:
50 TOPIC:-
292003 KNOWLEDGE:
K1.04 QID:
NEW Which one of the following percentages of fuel undergoing fission in a reactor will result in the largest reactc:: core effective delayed neutron fraction?
-90%
7%
3%
. B.
_80%
6%.
14%
C.
70%
7%
23%
D.
60%
6%
34%
ANSWER:
A.
l' 4
e. _ _
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOZER 1997 BWR - FORM A QUESTION:
51 TOPIC:
292003 KNOWLEDGE:
K1.06 QID:
B1250 Two reactors are identical in every way except that reactor A is at the end of core life and reactor B is at the beginning of core life.
Both reactors are **itical at 10-5% power.
If the same amount of positive reactivity,s added to each reactor at the same time, the point of adding heat will be reached first by.,
reactor because it has a delayed neutron fraction.
(
A.
A; larger B.
B; larger C.
A; smaller D.
B; smaller ANSWER:
C.
QUESTIOh6 52 TOPIC:
292004 KNOWLEDGE:
K1.02 QID:
B742 (Rev)
Under which one of the following conditions is a reactor core most likely to have a positive moderator temperature coefficient?
A.
Low coolant temperature at beginning-of-life B.
Low coolant temperature at end-of-life C.
High coolant temperature at beginning-of-life D.
High coolant temperature at end-of-life ANSWER:
B. l l
USNRC GENERIC FUNDAMENTALS EXAMINATION i
OCTOBER 1997 BWR - FORM A 9
' QUESTION:
53 TOPIC:=
292004 KNOWLEDGE:- -Kl.04 QID:-
B1553.
A reactor is operating at 70% power.
Which one of the-following will;directly result in a less negative fuel temperature
' coefficient?
(Consider only the effect of the change in each listed parameter.)
A.
Increase in Pu-240 inventory in the core B.
Increase in moderator temperature C.
Increase in fuel temperature D.
Increase in void fraction
~ ANSWER:
C.
QUESTION:
54 I
TOPIC:
292005 KNOWLEDGE:
Kl.04 OID:
B755 (Rev)
A reactor is critical below the point of adding heat (POAH) during
- a reactor startup at the end of core life.
Control rods are withdrawn for 20 seconds to establish a positive 30-second reactor period.
Reactor power will increase:
A.
continuously until control rods are reinserted.
B.
and stabilize at a value slightly below the POAH.
C.
temporarily, then stabilize at the original value.
D.
and stabilize at a value equal to the POAH.
ANSWER:-
D. -
USNRC GENERIC FUNDANENTALS ETANINATION OCTOBER 1997 BWR - FORN A QUESTION:
55
.-TOPIC:
292005
- KNOWLEDGE:
Kl.07
. QID:
NEW Which one of the following parameters typically has the greatest influence on the shape of a differential rod worth curve?
A.
Core radial neutron flux distribution B.
Core axial neutron flux distribution C.
Core xenon distribution D.
Burnable poison distribution ANSWER:
B.
1 9
QUESTION:
56 TOPIC:
292005 KNOWLEDGE:
Kl.09 QID:
B357 If the void fraction surrounding centrally located fuel bundles increases, the worth of the associated control rod (s) will:
A.
decrease, because more neutrons are able to travel from one fuel bundle to the next without being absorbed by the control rod.
B.
increase, because thermal neutrons will travel farther resulting in a larger fraction of thermal neutrons being
-absorbed by the control rod.
C.
decrease, because more neutrons are resonantly absorbed in the fuel as they are being thermalized resulting in fewer thermal neutrons.to-be. absorbed by the control rod.
- D.-
increase, because control rods are epithermal neutron absorbers and neutrons remain at higher energies longer due to the longer slowing down length.
ANSWER:
C..
Tm
.. =...... -
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTODER 1997 BWR - FORM A QUESTION:
57
-TOPIC:
292005 KNOWLEDGE:
Kl.12
-QID:
B656 During reactor power operations, the axial neutron flux shape is affected most by withdrawal of control rods and the radial neutron flux __ shape-is affected most by withdrawal of control rods.
4 A.-
shallow; shallow B.
deep; shallow C._
shallow; deep D.
deep;' deep ANSWER:
C 0
QUESTION:
58 TOPIC:
292006 KNOWLEDGE:
Kl.02 QID:
B5S Which one of the following lists the proper order of substances from the largest to the smallest microscopic cross sections for absorption of thermal neutrons?
A.
Gadolinium, U-235, Xe-135, U-238 B.
Gadolinium, Xe-135, U-235, U-238 C.
Xa-135, U-235, gadolinium, U-238 D.
Xe-135, gadolinium, U-235, U-238 ANSWER: D.
4 4
l -
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 2997 BWR - FORM A
. QUESTION:
59 TOPIC:
292006 KNOWLEDGE:
K1 04 QID ~
B1759 (Rev)
Which one of the following describes the change in core xenon-135 concentration immediately following a power increase from 50%
equilibrium conditions?
A.
Initially decreases due to the increased rate of xenon-135 radioactive decay.
B.
Initially decreases due to the increased absorption of thermal neutrons by xenon-135.
C.
Initially increases due to the increased xenon-135 production from fission.
D.
Initially increases due to the increased iodine-135 production from fission.
ANSWER:
B.
QUESTION:
60 TOPIC:
292006 KNOWLEDGE:
Kl.07 L-QID:
B1561 Which one-of-tbe following reactor startup' conditions requires the least amount of control rod withdrawal to attain reactor criticality during peak core xenon-135 conditions after a reactor scram from equilibrium core xenon-135 conditions?
A.
Scram from 20% power at beginning of core life (BOL)
B.
Scram from 20% power at end of core life (EOL)
C.
Scrum from 100% power at BOL D.
Scram from 100% power at EOL ANSWER:
A.
USNRC GENERIC FCPNWALS EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:
61 TOPIC:-
292006 KNOWLEDGE:
K1.10 QID:
B1461 A-reactor has been operating at 100% power for two months when a
-reactor scram occurs.
Four hours later, the reactor is critical and stable at 10% power..
Which one of the following operator actions is required-to maintain reactor power at 10% over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />?
A.
Add positive reactivity during the entire period B.
Add negative reactivity during the entire period C.
Add positive reactivity, then negative reactivity D.
Add negative reactivity, then positive reactivity ANSWER:
C.
1 QUESTION:
62 TOPIC:
292006 KNOWLEDGE:
K1.12 QID:
B2159 (Rev) 1 Twenty-four' hours after a reactor scram from a long-term, steady-state, 100% power run, the core xenon-135 concentration will be approximately:
A.
the same as at the time of the scram and decreasing.
B.
the same as at the time of the scram and increasing.
C.
50% lower than at the time of the scram and decreasing.
D.
50% higher than at the time of the scram and increasing.
ANSWER:
A......
USNRC GENERIC FUNDAMENTALS EEANINATION OCTOCER 1997 CWR - FORM A QUESTION:
63 TOPIC:
292006-KNOWLEDGE:
K1.14
-QID:
B62-(Rev)
A reactor is operating at 80% power following a power reduction from 100% over a one-hour period.
To keep reactor power at 80%
over the'next three hours, the operator must control rods or recirculation flow rate.
A.
insert; increase B '.
insert; decrease
^
C.
withdraw; increase D.
withdraw; decrease ANSWER:
C.
QUESTION:
64 TOPIC:
292008 KNOWLEDGE:
Kl.03 OID:
B1766 A reactor startup is in progress with a current K.tr of 0.95 and a current equilibrium source range count rate of 150 cps.
Which one of the following equilibrium count rates will occur when K rt o
becomes 0.987 A.
210 cps B.
245 cps C.
300 cps D.
375 cps
' ANSWER:
D.
PROOF:
CR /CR (1 - K ) / (1 - Ka)
=
2 3
3 CR
=
2
(.05/.02) 150 375
=
USNRC QENERIC FUNDAMENTALS EXAMI1RTION OCTOBER 1997 EWR - FORN A QUESTION:
65 TOPIC:
-292007 KNOWLEDGE:
Kl.03
-QID:
B1163' Refer to the drawing of K.tr vercus core age (see figure below).
The decrease in K.et from point 1 to point 2 is primarily caused by:
A.
depletion of fuel.
B.
burnout of burnable poisons.
C.
initial heat-up of the reactor.
D.
buildup of fission product poisons.
ANSWER:
D.
3 K,gg i
2 4
Core Age K,97VERSUS CORE AGE
h USNRC GENERIC FUNDAMENTALS EXAMINATION OCTO!ER 1997 CWR - FORM A l
4 6 - - _ _ _ - _ _ _ _ _ _ _ - _ _
USNRC ramrmtIC FUNDMENTALS EXAMINATION OCTOBER-1997 BWR - FORM A QUESTION:
66.
TOPIC:.
292008
+
KNOWLEDGE:
Kl.04 QID:
B67 (Rev).
As a reactor approaches criticality during a reactor startup it takes. longer to reach an equilibrium neutron count rate after each control rod withdrawal due'to the increased:
A.
length of time required to complete a neutron-generation.
B. : number of neutron generations required to reach a stable neutron level.
C.
length of time from neutron birth to absorption.
D.
fraction of delayed neutrons being produced as criticality is approached.
ANSWER:
B.
QUESTION:
67 TOPIC:
292008
. KNOWLEDGE:
Kl.08 QID:
-B1069 f
l-A' reactor is critical just below the point of adding heat (POAH) at a temperature of 160*F.
Which one of the following will result in reactor power increasing and stabilizing at the POAH?
(Assume a negative moderator temperature coefficient.)
A.
Reactor recirculation flow increases 10%.
B.
Reactor coolant temperature increases 3*F.
C.
.A single control rod moves in one notch.
D.
Core xenon-135 concentration decreases.
ANSWER:
D.
4
- l
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR'- FORM A QUESTION:
68 TOPIC:
292008 KNOWLEDGE:
Kl.12 QID:
B133 (Rev)
A reactor startup is in progress and criticality has just been achieved.
After: recording critical rcd height, the operator withdraws control rods for '0 seconds to establish a positive 2 second reactor period.- One minute later (prior to the. point of adding heat) the operator inserts the same control rods for 25 seconds.
During the insertion, the reactor period will become:
A.
infinity during the entire period of control rod insertion.
B.-
negative after the control rods pass through th.' critical rod height.
C.
negative just as the control rods pass through the critical rod height.
D.
negative before the control rods pass through the critical rod height.
ANSWER:
D.
QUESTION:
69 TOPIC:
292008 KNOWLEDGE:
Kl.15 QID:
B469 A reactor is stable at the point of adding heat (POAH) with the reactor coolant at 160*F during the reactor heat-up and pressurization phase of a reactor startup.
Control rods are withdrawn a few notches to raise reactor power and establish a heat-up rate.
If no further control rod withdrawal occurs, reactor power will:
(Assume no voiding occurs.)
A.
remain stable until voiding begins to occur.
B.
increase until the control rods are reinserted.
-C.
decrease and stabilize at a subcritical power level.
D.
decrease and stabilize at the POAH.
ANSWER:
D...
USNRC GENERIC Ftpm1NALS EXANINATION OCTO ER 1997 BWR - FORM A QUESTION:
70 TOPIC:
292008 KNOWLEDGE:
Kl.18 QID:
B1371-(Rev)
With a reactor on a constant period, which one of the following power changes requires the shortest time'to occur?
A.
1% power to 4% power B.
5% power ~to 15% power C.
20% power to 35% power D.-
40%_ power to 60% power ANSWER:
D.
QUESTION:
71 TOPIC:
292008 KNOWLEDGE:
K1.22 QID:
B971 A plant is operating at 85% power when a failure of the cteam pressure control system opens the turbine control valves to admit 10% more steam flow to the main turbine.
No operator actions occur and no protective system actuations occur.
How will reactor power respond?
(Assume the valves remain in the failed position.)
4 A.
Increase until reactor power matches the new steam demand B.
Increase continuously and exceed reactor protection set points C.
Decrease and stabilize at'a lower power level and steaming rate D.
Decrease and stabilize at a critical power level below'the point of adding heat-t ANSWER:
C..
l
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTODER 1997 BWR - FORN A QUESTION: -
72-TOPIC:
292008 KNOWLEDGE:
K1.30 QID:-
B131 (Rev)
A reactor has been operating at 100% power for several weeks-when a reactor scram occars.
How much time will be required for core heat production to'3ecrease to 1% following the scram?
A.
1 to 8 days B.
1 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C.
- 1 to 8 minutes D.
1 to 8 seconds ANSWER:
B.
a 9
6 l
l.
--r-.
l USNRC GENERIC FUNDAMENTAL 3 EXAMINATION OCTO ER 1997 BWR - FORM A QUESTION:
73 TOPIC:
293001 KNOWLEDGE:
K1.03 QID:
B1174 Refer to the drawing of four identical tank differential pressure level detectors (see figure below).
The tanks are identical and are presently at 2 psig overpressure and the same constant water level and a temperature of 60*F.
They are surrounded by. atmospheric pressure.
All level detectors have been calibrated and are producing the same level indication.
A leak in the top of each tank causes a complete loss of overpressure in both tanki.
Which level detector (s) will produce the lowest level indication?
A.
1 B.
2 C.
1 and 4 D.
2 and 3 ANSWER:
D.
M*:::.M
"'l WF
..y;..
..g;..
M"=:.m
a.*".:::'*
=*( / F ay;..
..g;..
TANK OtFFERENTIAL PRES $U8tE LEVEL DETI'CTORS _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ ___-__ _ __- - __ - -
USNRC l3NERIC FUNDAMENTALS EXAMINATION OCTOBER'1997 BWR - FORM A QUESTION:
74-TOPIC:
29'003 KNCWLEDGE:
Km.J9 QID:
B1574 Consider'a steam-water mixture with a current quality of 79%.
If pressure renains constant and heat is added to the mixture, the temperature of the mixture will and the quality of the mixture will (Assume the mixture remains saturated.)
A.
remain the same; increase B.
remain the same; remain the same C.
increase;-increase
-D.
increase; remain the same ANSWER:
A.
QUESTION:
75 TOPIC:
293003 KNOWLEDGE:
K1.23 QID:
NEW-1.0 x 10' lbm/hr saturated steam at 30% steam quality is leaving a main turbine and entaring a condenser at 2.0 psia.
Condensate is entering the hotwell at 118 degrees F.
Which one of the following is the approximate condenser heat transfer rate?
A.
3.1 x 108 Btu /hr B,
- 5. 8 x '10' Btu /hr C.
7.2 x 10' Btu /hr
-D.
9.9 x 10'- Btu /hr ANSWER:
A.
PROOF:
From steam tables:
Exhaust steam enthalpy is 1116.1 -
(0.7)(1022.2)~= 400.56 Btu /lbm From steam tables:
Condensate enthalpy is 86 Btu /lbm Q = m-dot delta-h Q = -(1,000,000 lbm/hr) (400.6 - 86 Btu /lbm)
Q = 314,600,000 Btu /hr -
l USNRC GENERIC FUNDAMENTALS EZAMINATION OCTOBER 1997 BWR - FORM A
-QUESTION:
76 TOPIC::
293004 KNOWLEDGE:
K1.04
.QID:
B376 Refer to the drawing'of a steam-jet air ejector (see figure below).
In' the figure of an operating steam jet air ejector, steam flowing-from D to E undergoes a pressure and a velocity A.
decrease; decrease B.
decrease; increase C.
increase ~; increase D.
increase;. decrease ANSWER:
D.
AB C
D E
l l
l fib N;
4 g
h) i i DISCHARGE STEAM
'""% %sl %utaw
% STEAM N.
A7Mh5)h ya m A" qi 1
AIR EMATh
'li L;
?
6 a
AIR & STEAM STEAM JET AIR EJECTOR. _. _
i i
USSIRC GEIS 'IC FUlmAREElfTALS EXAttZat&TIOIt l
OcstaER 1997 SWR - FORat A l
QUEST 20N:
77 TOPIC:
293004 hNOWLEDGE:
Kl.12 QID:
.B1876 (Rev)
Condensate depression is the process of A.
removing condensate from turbine exhaust steam, B.
spraying condensate into turbine exhaust steam.
i C.
heating turbine exhaust steam above its saturation temperature.
D.
cooling turbine exhaust steam oelow its saturation temperature.
ANSWER:
D.
i
.t l
QUESTION:
78 TOPIC:
293005 KNOWLEDGE:
Kl.05 QID:
B278 Which one of the following is the most probable location for superheated steam in a boiling water reactor steam cycle that uses moisture separator reheaters?
A.
The inlet of the high pressure turbine B.
The inlet of the low pressure turbines C.
The outlet-of the high pressure turbine D.
The outir,C of the low pressure turbines ANSWER:
B.
t.
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:
'/ 9 TOPIC:
191004 KNOWLEDGE:
Kl.14 GID:
B1878 (ney)
Refer to the drawing of four sets of centrifugal pump operating curves (see figure below).
Each set of curves shows the results of a change in pump / system operating conditions.
Two identical constant-speed centrifugal pumps are operating in parallel in an open system when one pump trips.
Which set of operating curves depicts the "before" and "after" conditions des ribed above?
1.
B.
2.
C.
3.
D.
4.
INSWER:
A.
PUMP PUMP HEAD HEAD FLOW FLOW
- UMP PUMP HEAD HEAD FLOW FLOW EE CENTRIFUGAL PUMP OPERATING CURVES l
_ =.
... ~. -
i USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BNR - FORN A i
QUESTION:
80 L
TOPIC:
293006 KNOWLEME:
Kl.19 QID:
B1181 A plant is operating at full power when a 200 gpm reactor coolant i
leak occurs, which results in a reactor scram and initiation of i
emergency coolant injection.
Reactor vessel pressure stabilizes at 900 psia and all injection pumps are operating with all pump miniflow paths isolated.
The shutoff heads for the pumps are as i
follows:
High pressure coolant injection (HPCI) pumps: 1200 psia Low pressure coolant injection (LPCI) pumps:
200 psia Which pumps must be stopped quickly and why?
-A.-
HPCI pumps to avoid pump overheating caused by high flow B.
HPCI pumps to avoid motor overheating caused by high flow C.
LPCI pumps to avoid pump overheating caused by low flow f
D.
LPCI pumps to avoid motor overheating caused by low flow ANSWER: C.
r 1. -.
0 USMRC GENERIC FUNDhMENTAL5 EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:
81 i
TOPIC:
293006 KNOWLEDGE:
K1.29 QID:
NEW Water at 90 degrees F and 50 psig is flowing through a 10-inch diameter pipe at 100 lbm/ hec.
The pipe then splits into two pipes, a 4-inch diameter pipe and an 8-inch diameter pipe.
Disrcgarding any flow restrictions other than pipe size, which one of the following lists the approximate flow rates through the 4-inch and 8-inch diameter pipes?
4-inch Pipe 8-inch Pipe
.(1bm/sec)
(1bm/sec)
A.
20 80 B.
25 75 C.
30 70 D.
33 67 ANSWER:
A.
PROOF:
m = pAv mi + m2 = 100 pAlv + pA2v = 100 pv(Al +A2) 100
=
pv(80) = 100 pv = 100/80 mi a pvAl ml = 100/80 (16) i ml = 1600/80 = 20 lbm/sec
-m2 = pvA2 m2 = 100/80-(64)-
ml = 6400/80 = 80- lbm/sec
+--*t up y
y9
-wg-,.
s 3
e pe
-g-
,+-ti,-w-m-w---.e-w-,
-W-'e=
Pe h v e-r-wre'
~--N' eww--rw
=ww
._. ~. _
USWRC GEIEERIC FUttDhbEATALS EXAMIttATIOtt OCTOBER 1997 BWR - FORBI A QUESTION:
82 TOPIC:
293007 KNOWLEDGE:
Kl.01 QID:
NEW Which one of the following describes a heat transfer process in which convection is the most significant heat transfer mechanism?
I A.
From the reactor fuel to the core carrel during core uncovery B.
Through the tube walls in a main condenser during normal operation at 100% power C.
From the reactor fuel to the steam outlet of.the reactor vessel during a station blackout D.
From fuel pellet centerline to fuel clad during normal operation at 100% power 4
ANSWER:
C.
QUESTION:
83 TOPIC:
293007 KNOWLEDGE:
Kl.02 QID:
B1682 The buildup of fission gases in a fuel rod causes thermal conductivity of the fuel pellets to and thermal conductivity of the fill gas to (Consider only the direct effect of the fission gases.)
' A.
decrease; decrease B.
decrease; increase C.
increase; decrease D.
increase; increase ANSWER:
A.
57 -
+w-
- e+-e
=
.-ee,c y
g-m
'er.e,-
y a-e.--
wt-e m
e-
---+s-vs aey-'---e e--vem s
yy-s-*y sy.-w-w 7
e
'r
- r FW T
'-r 7?'"-
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:
84 TOPIC:
293007 KNOWLEDGE:
K1.13 QID:
B2183 (Rev)
The power range nuclear instruments have been adjusted to 100%
based on a calculated heat balance.
Which one of the following will result in indicated reactor power being lower than actual reactor power?
A.
The feedwater temperature used in the heat balance calculation was 20*F higher than actual feedwater temperature.
B.
The reactor recirculation pump heat input term used in the heat balance was 10% lower than actual.
C.
The steam and feedwater flow rates used in the heat balance calculation were 10% higher than actual flow rates.
D.
The operator miscalculated the enthalpy of the steam exiting the reactor vessel to be 10 Btu /lbm higher than actual.
ANSWER:
A.
QUESTION:
85 DELETED.
r
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BNR - FORN A QUESTION:
86 TOPICS 293008 KNOWLEDGE:
K1.01 QID:
B1183 Refer to the drawing of a pool boiling curve (see figure below).
In which region (s) of the curve does the reactor normally operate to transfer heat from the fuel cladding to the coolant at 100%
power?
A.-
Region I only
.B._
Regions I and II C.
Region II only D.
Regions II and III ANSWER: B.
l ll lil N
Loa HEAT FLUX loo AT POOL EKNUNG CURVE l
l L
_-...__._._.m USNRC GESIERIC FUBIDMEMOTALS EXAMINATIOtt OCTOBER 1997 BWR - FORM A QUESTION:
~87 TOPIC:
293008 KNOWLEDGE:
Kl.08 QID:
B287 (Rev) i The maximum convective heat transfer coefficient exists just prior to the beginning of:
4 A.
bulk boiling.
i B.
departure from nucleate boiling.
C.
subeJoled nucleate boiling.
' D.
saturated-nucleate boiling.
ANSWER: B.
QUESTION:
88 TOPIC:
293008
_ KNOWLEDGE:
Kl.09 QID:
B987 (Rev) i Which one of the following describes the conditions in a fuel channel that is experiencing transition boiling?
A.
Complete steam-blanketing of the fuel rod surface i
B.
Alternate wetting and drying of the fuel rod surface C.
Steam bubbles form and collapse on the fuel rod surface 1
D.
Steam bubbles form on the fuel rod surface and are swept away by subcooled bulk coolant
' ANSWER:
B.
i
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BMI - FORM A i
QUESTION:
-89 TOPIC:
293008 KNOWLEDGE:
K1.17 QID:
B1588 A reactor is operating at steady state 90% power.
Which one of the following will cause the two-phase coolant flowing upward in a fuel channel to become closer to the onset of transition boiling?
(Assume reactor power does not change unless stated.)
A.
Reactor pressure increases.
B.
Recirculation flow increases.
C.
Feedwater temperature decreases.
D.
Associated bundle power decreases.
ANSWER:
A.
i QUESTION:
90 TOPIC:
293008 KNOWLEDGE:
Kl.21 QID:
B1689 Given the following conditions:
10 lbm mixture of vapor and liquid Steam quality = 30%
Pressure
= 1,000 psia Which one of the following approximates the void fraction?
A.
10.1%
B.
11.3%
C.
88.7%
D.
89.9%
ANSWER:
D.
PROOF:
Void Fraction =
Volume Steam l' l
......... - ~...
. _ - -. -.. ~. - -
USMRC GEIRRIC FUNDAMENTALE EXAMINATIOtt O N BER 1997 BWR - FORM A Volume Steam + Volume Water
.3(.44596)
=
.3(.44596) +.7(.02159)
=
.133788
.133788 +.015113
.133788
=
.148901
=.8985 = 89.9%
9 9
i f
+. _ _
USNRC GENERIC FUNDMIENTAL3 EXAMINATION OCTO ER 1997 BWR - FORM A QUESTION:
91 TOPIC:
293008 KNOWLEDGE:
Kl.30 QID.
B1790 Two reactors, A and B, are operating at rated power with neutron flux radially peaked in the center of each core.
Reactors A and B are identical except that reactor A has core orificing and reactor B does not.
Both reactors have the same control rod pattern and density.
Compared to the center fuel but<"i in reactor A, the center fuel bundle in reactor.B will have t'e critical power and the coolant flow rate.
A.
lowest; lowest B.
lowest; highest C.
highest; lowest D.
highest; highest ANSWER:
.A.
QUESTION:
92 TOPIC:
293009 KNOWLEDGE:
Kl.11 QID:
B1793 (Rev)
Which one of the following describes the basis for the 2200*F maximum fuel clad temperature limit?
2200*F is approximately 500*F below the fuel clad melting A.
temperature.
B.
The rate of the zircaloy-steam reaction-becomes significant at temperatures above 2200*F.
C.
If-fuel clad temperature reaches 2200*F, the onset of l
transition boiling is imminent.
D.
The differential expansion between the fuel pellets and the fuel clad becomes excessive above 2200*F-ANSWER:-B.
--63.-
i USNRC omarEMIC FUNDMENTALS EXANINATION OCTOBER 1997 BWR - FORN A Q
QUESTION:
93 TOPIC:
293009 KNOWLEDGE:
Kl.07 QID:
B295 Operating a reactor below the linear heat generation rate thermal limit prevents:
A.
cracking of the fuel cladding due to high stress from fuel pellet expansion.
B.
melting of the fuel claG.'ing due to cladding temperature exceeding _2200*F during an anticipated transient without a scram.
C.
cracking of the fuel cladding due to a lack of cooling caused by departure from nucleate boiling.
D.
melting of the fuel cladding due to a lack of cooling following a loss of coolant accident.
ANSWER:
A.
QUESTION:
94 TOPIC:
293009 KNOWLEDGE:
Kl.01 QID:
B1092 In a reactor operating at full power, the fuel bundle with the highest power always has the:
1 A.
greatest critical power ratio.
B.
greatest radial peaking factor.
C.
smallest linear heat generation rate.
D.
smallest maximum average planar linear heat generation rate.
ANSWER:
B.
t 1..
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTO ER 1997 BWR - FORM A QUESTION:
95 TOPIC:
293009 FJJOWLEDGE:
Kl.16 QID:
B495 Refer to the drawing of a fuel rod and coolant flow channel at the beginning of core life (see figure below).
Given the following initial core parameters:
Reactor power 100%
=
T ot ot 500*F
=
e T,,,3 c...,tio, 2500*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*F B.
1300*F C.
1400*F D.
1500*F ANSWER:
D.
r% : -
CLAD
%J FUEL PELLET n
ws P%
l cootaur Coouur FLOW 4
FLOW I
t FUEL ROD AND COOLANT FLOW CHANNEL l 1
- -.. _ - ~ --.
USMRC GENERIC FUNDAMENTALS EXAMINATION l
OCTOBER 1997 BWR - FORM A 1
o i
I PROOF:
Tet
= T, 3.,,s + 6T l
AT/2 = (2500 - 500)/2 2000/2.
=
1000
=
~
t.'Ta =--500 + 1000 i
1500*F
=
.f.
6 R
6,
_ - _ _--_- = -.- - _
I
'USNRC GIGIERIC FUNDAMENTALS EZAMINATION OCTOZER 1997 BNR - FORN A
. QUESTION 96 TOPIC:
293009 KNOWLEDGE:
Kl.26 QID:
B1396 How is critical power affected when the axial power distribution in I
a fuel bundle shifts from bottom-peaked to top-peaked?
A.
Critical power increases to a new, higher value.
B.
Critical power increases temporarily, then returns to its initial value.-
C.
Critical power decreases to a new, lower value.
D.
Critical power decreases temporarily, then returns to its initial value.
.. ANSWER:
C.
QUESTION:
97 TOPIC:
293009 KNOWLEDGE:
Kl.30 QID:
B2193 (Rev)
A step increase in reactor power results in a fuel rod surface temperature increase from 570*F to 590*F at steady state conditions.
The fuel thermal time constant is 6 seconds.
Which one of the following is the approximate fuel rod surface temperature 6 seconds after the power change?
A.
574*F B.
577'F C..
580*F D.
583*F ANSWER:
D.-
PROOF:
Tr = Ti+ 0. 632 (Te - T )
Te = 570 + 12. 64 1
Te = 570 + 0.622 (590
.570)
Te = 582. 64 i
-- 67'-
L e
c
-- o e r
=
,_.~.-4_.-
~. _
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:
98 f
TOPIC:
293009 KNOWLEDGE:
Kl.43 QID:
B1298 (Rev)
If reactor feedwater temperature suddenly increases by 10*F during operation at 75% power, critical power will and bundle power will (Assume the reactor does not scram.)
A.
increase; increase e
e B.
increase; decrease i
C.
decrease; increase D.
decrease; decrease
' ANSWER:
D.
1 4
QUESTION:
99 TOPIC:
293010 KNOWLEDGE:
Kl.02 QID:
B1500 (Rev)
The nil-ductility transition temperature is that t
.perature:
A.
below which vessel failure is imminent.
B.
above which vessel failure is imminent.
below which the probability of brittle fracture significantly C.
increases.
above which the probability of brittle fracture significantly D.
increases.
ANSWER:
C.
W,
USNRC GENERIC FUNDMEENTALS EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:
100 TOPIC:
293010 KNOWLEDGE:
Kl.04 QID:
B899 (Rev)
A heatup stress applied to the reactor vessel ist A.-
tensile at the inner wall and compressive at the outer wall.
B.-
tensile-across the entire wall.
C.
compressive at the inner wall and tensile at the outer wall.
D.
compressive'across the entire wall.
ANSWER: C.
J
- i
O 000 FINAL ANSWER KEY 000 OCTOBER 1997 NRC GENERIC FUNDAMENTALS EXAMINATION PRESSURIZED WATER REACTOR - ANSWER KEY FORM ANS FORM ANS FORM ANS FORM ANS A
B A
B A
B A
B 1
29 B
26 54 D
51 79 D
76 4
A 2
30 D
27 55 A
52 80 A
77 5
B 3
31 B
28 56 A
53 81 A
78 6
A 4
32 C
29 57 C
54 82 B
79 7
B 5
33 D
30 58 A
55 83 C
80 8
B 6
34 A
31 59 A
56 84 D
81 9
C 7
35 A
32 60 D
57 85 B
82 10 A
8 36 A
33 61 D
58 86 A
83 11 B
9 37 B
34 62 D
59 87 C
84 12 C
10 38 A
35 63 B
60 88 A
85 13 B
11 39 A
36 64 B
61 89 D
86 14 B
12 40 C
37 65 C
62 90 D
87 15 D
13 41 D
38 66 C
63 91 A
88 16 D
14 42 D
39 67 C
64 92 C
89 17 C
15 43 A
40 68 D
65 93 C
90 18 D
16 44 A
41 69 A
66 94 D
91 19 B
17 45 B
42 70 B
67 95 C
92 20 B
18 46 D
43 71 A
68 96 D
93 21 C
19 47 B
44 72 D
69 97 B
94 22 C
20 48 B
45 73 D
70 98 C
95 23 B
21 49 D
46 74 A
71 99 8
96 24 C
22 50 D
47 75 C
72 100 B
97 25 B
23 51 B
48 76 A
73 1
B 98 26 D
24 52 B
49 77 A
74 2
D 99 27 C
25 53 C
50 78 C
75 3
A 100 28 C
a
--"an
,e
- k ENCLOSURE 2 l
t I
i l
i I
l l
l l
t i
i i
l l
UNITED STATES NUCLEAR REGULATORY COMMISSION g
PRESSURIEED WATER REACTOR GENERIC FUNDANENTALS EXANINATION OCTOBER 1997 - FORN A o
September 12, 1997 Please Print Names Facility:
Docket No.:
Start Time:
Stop Time:
INSTRUCTIONS TO APPLICANT Answer all the test items using the answer sheet provided.
Each item has equal point value.
A score of at least 80% is required to pass this portion of the written licensing examination.
All examination papers will be collected 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> after the examination starts.
This examination applies to a
typical pressurized water reactor (PWR) power plant.
SECTION QUESTIONS
% OF TOTAL SCORE COMPONENTS 1 - 44 REACTOR THEORY 45 - 72 THERMODYNAMICL-73 - 100 TOTALS 100 All work done on this examination is my own.
I have neither given nor received aid.
Applicant's Signature
e i
RULES AND GUIDELINES FOR TME GENERIC FUNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:
NOTE:
The generic term " control rod" refers to the length of neutroa absorber material that can be positioned by the i
operator to change core reactivity.
1.
Print your. name in the blank provided on the cover sheet of the examination.
2.
Fill in the name of your facility.
3.
Fill in your individual docket number.
4.
Fill in your start and stop times at the appropriate time.
5.
Two aids are provided for your use during the examinations (1)
An equations and conversions sheet contained within the examination copy, and (2)
Steam tables provided by your proctor.
6.
Place your answers on the answer sheet provided.
Cicdit will only be given for answers properly marked on this sheet.
Follow the instructions for filling out the answer sheet.
j 7.
Scrap paper will be provided for calculations.
8.
Cheating on the examination will result in the auts.natic forfeiture of this examination.
Cheating could also result in severe penalties.
9.
Restroom trips are limited.
Only ONE examinee may leave the room at a time.
In order to avoid the appearance or possibility of cheating, avoid all contact with anyone outside of the examination room.
- 10. Af ter you have completed tbt examination, sign the statement on t
the cover sheet indicating that the work is your own and you have not received or been given any assistance in completing the examination.
- 11. Turn - in your examination materials, _ answer sheet on top, followed by the examination booklet, then examination aids steam table booklets, handouts and scrap paper used during the examination.
- 12. After turning in your examination materials, leave the examination area, as defined by the proctor.
If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeited. -
i GENERIC FUNDAMENTALS EXAMINATIOst EQUATIONS AND CONVERSIONS HANDOUT SHEET l
EQUATIONS 1
Q =theoT P = P.10 8*"
l p
0 = rho h P = P,e /u tt l
i Q = UAAT A = A,e'A'
.3 g, bt Orc CRefo = S/ (1 - K rt)
CR (1 - K.f ra)
CR (1 - Kerra)
=
3 2
AT. di o,,
1/M = CR /CRx i
K.tr
- 1/(1 - P)
IRW= $*,/ $',,
p=
(K.,, - 1) /Kerr F = PA SUR = 26.06/t rh = PAV
_0~P A
p Wew = thaPU E = IR t'
p P=-+
1+Ag L;.f. = Net Work Out/ Energy In
~
~
- g. = 1 x 10-' seconds 2ge ge A.,, = 0.1 seconds 1 8
g, = 32.2 lbm-f t/lbf-sec CONVERSIONS 3.41 x 10' Btu /hr 1 Curie 1 Mw
=
3.7 x 10' dps 2
=
1 hp 2.54 x 108 Btu /hr 1 kg
=
2.21 lbm
=
1 Btu =
778 ft-lbf 1 gal..., =
8.35 lbm
- C (5/9) (*F - 32) 1 f t
.t.,
8
=
7.48 gal
=
'F (9/5) ('C) + 32
=
1 3-
=...
_ - _ ~ -
. -. - ~..
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTosER 1997 PNR ~ FORN A QUESTION:
1 TOPIC:
191001 KNOWLEDGE:
K1.02 QID:
P1504 Which one of the following is a difference between a typical relief valve and a typical safety valve?
A.
The actuator closing spring on a relief valve is in a compressed state whereas the actuator closing spring on a safety valve acts in tension.
B.
A relief valve gradually opens as pressure increases above the setpoint pressure whereas a safety valve fully opens at the setpoint pressure.
~
~
C.
Relief valves are capable of being gagged whereas safety valves are not.
D.
The blowdown of a relief valve is greater than the blowdown of a safety valve.
ANSWER:
B.
QUESTION:
2 TOPIC:
191001 KNOWLEDGE:
Kl.07 QID:
P503 (rev)
Which one of the following valves is used to control the direction of fluid flow and prevent backflow in a system?
A.
Gate valve B.
Relief valve C.
Globe valve D.
ANSWER:
D.
USMRC GENERIC FtpmmWALS EXAMINATION OCTOB2h 1997 FNR - FORM A QUESTION:
3 TOPIC:
191001 KNOWLEDGE:
Kl.08 QID:
P1405 Refer to the cutaway-view drawing of a valve (see figure below).
Which one of the following describes the type of valve shown?
A.
Rising-stem gate valve B.
Nonrising-stem gate valve C.
Rising-stem globe valve
~
D.
Nonrising-stem globe valve ANSWER:
B.
N b
( $
t b
W<
r 4
/ g,,
VALVE CUTAWAY-VIEW l.
USIIRC GENERIC FUNDhMENTALei EXAMINATION OCTOBER 1997 FWR - FORN A QUESTION:
4 TOPIC:
191001 KNOWLEDGE:
Kl.09 QID:
P1104 (Rev) i Gate valves generally are not used to throttle fluid flow because:
A.
rapid changes in fluid direction through the valve cause a large unrecoverable system head loss.
B.. gate valves experience stem leakage when partially open.
C.. the turbulent flow created by a partially opened gate valve-causes excessive seat and disk wear.
D.
-the large size of the valve disk. requires an oversized 1
actuator to position the valve accurately.
ANSWER:
C.
QUESTION:
5 TOPIC:
191002 KNOWLEDGE:
Kl.02 QID:
P705 A steam flow measuring instrument uses density compensation and square root extraction to convert the differential pressure across the flow element to lbm/hr.
The purpose of square root extraction in this flow measuring instrument is to convert to A.
volumetric flow rate; mass flow rate B.
volumetric flow rate; differential pressure C.
differential pressure; mass flow rate D.
differential pressure; volumetric flow rate ANSWER:
D.
i
! L L
l
USMRC GENERIC FUNDAMENTALS unMTMATION OCTosER 1997 PNR - FORM A QUESTION:
6 TOPIC:
191002 KNOWLEDGE:
Kl.04 QID:
P1608 Refer to the drawing of a horizontal pipe elbow (top view) in an operating water system (see figure below).
Three separate bellows differential pressure flow detectors are connected to taps A, B, C, and D-as follows:
DETECTOR TAPS AD A and D BD B and D CD C and D Assuming zero head loss in this section of pipe, how will the detectors be affected if tap D ruptures?
A.
All detectors will fail low.
B.
All detectors will fail high.
C.
Two detectors will fail low and one will fail high.
D.
Two detectors will fail high and one will fail low.
ANSWER:
A.
til1 A
B C
ll FLOW b
D I-l l
PIPE EL80W. TOP VIEW l -
USNRC tamarmtIC FUNDAMENTALS EXAMINATION OCTOMR 1997 PWR - FORft A -
l QUESTION:
7-TOPIC:
191002 KNOWLEDGE:
K1.05 QIDt P908 Which one of the following flow measuring devices produces the i
largest unrecoverable head loss when used in un operating fluid system?-
A.
Orifice B.
Venturi C.
Pipe elbow D.
Flow nozzle ANSWER: A.
QUESTION:
8 TOPIC:
191002 KNOWLEDGE:
Kl.17 QID:
P1612 A reactor is shut down at 100 cps in the source /startup range when a loss of coolant accident occurs.
Which one of the following describes excore source /startup range neutron level l
indication as homogeneous core voiding increases from 20% to 40%?
I i
A.
Increases because more neutron leakage is occurring B.
Decreases because less neutron leakage is occurring C.
Increases because Kerr is increasing D.
Decreases because K.
is decreasing l
ANSWER:
A.
l.
UstatC GENERIC FUNDMEENTALS EXAMIKkTION OCTOBER 1997 PHR - FORN A QUESTION:
9 TOPIC:
191002 KNOWLEDGE:.K1.06 QID:
P608 (Rev)
Refer to the drawing of two tank differential pressure (D/P)
~1evel indicators (see figure below).
Two D/P level indicators are installed on a large water storage tank.
Indicator 1 was calibrated at 100*F water temperature and indicator ? was calibrated at 200*F water temperature.
Assuming both are on scale, which indicator will indicate the higher level?
A.
Indicator 1 at all water temperatures B.
Indicator 2 at all water temperatures C.
Indicator 1 below 150*F, indicator 2 above 150*F D.
Indicator 2 below 150*F, indic ta or 1 above 150*F ANSWER:
B.
TO A MOS RE
/
WATER
/
/
+
+
1 i
I l
TANK OtFFERENTIAL PRESSURE LEVEL INDICATORS 9--
y 4
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOCER 1997 PWR - FORM A I.
QUESTION:
10 TOPIC:
191002 KNOWLEDGE:
Kl.08 QID:
NEW Refer to the drawing of a tank with a differential pressure level detector (See figure below.).
The level detector was calibrated with reference leg and tank contrats temperature at 70'F.
An increase in ambient temperature causes the temperature of the reference leg and tank contents to increase to 110*F.
With the temperature of the reference leg and tank contents stable at 110'F, current level indication will be:
A.
higher than initial due to reference leg spill over.
B.
higher than initial due to expansion of tLnk contents.
C.
the same as initial due to offsetting density changes in the reference leg and tank contents.
D.
the same as initial due to the reference leg being connected to the upper portion of the tank.
ANSWER:
A.
REFERENCE LEG FILL CONNECTION GAS OR VAPOR PRESSURE
^
EQUAll21NG 9
VALVE
/
r
[
/
z m2 DETECTOR TANK DIFFERENTIAL PRESSURE LEVEL DETECTOR 1
... ~..
US3!RC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
11 TOPIC:
191002 KNOWLEDGE:
K1.12 '
. QID:-
P510-(Rev)
Refer to the drawing of a bellows-type pressure detector (see figure below).
A bellots-type preesure detector with its low-pressure si.de vented to. containment atmosphere is.being used to measure pressurizer pressure.
A decrease in the associated pressure indication will be caused by either a containment pressure or a A.
increases ruptured bellows B.
increase; broken spring C.
decrease; ruptured bellows D.
decrease; broken spring ANSWER:
A.
/ VEABLEWALL MO SEAUNG
(
/)
CONNECTION Batows BELLOWS TYPE PRESSURE DETECTOR i
'H
,. 1
USNRC GENERIC FUNDANENTALS EXAMINATION OCTOBER 1997 PWR - FORM A l
-QUESTION:
12 TOPIC:
191002-KNOWLEDGE:
K1.13 OID:
P1412 (Rev)
Refer to the drawing of a simple thermocouple circuit (see figure below).
Circuit p..a h e indication is currently 350*F.
If an ambient dgey;f ae lowers reference (cold) junecion temperature temperat a by 10*F, t.
' t ed imperature indication will be:
(Assumo measuring,-
cti < tearerature remains constant.)
A.
340*F.
B.
350*F.
C.
360*F.
D.
370*F.
ANSWER:
C.
e 3
h s-(
voi.TAoe MEASURI y
JUNCTION REFERENCE [COJ]
POTENT W ETER JUNCTION (TEMPERATURE INDICATION)
SIMPLE THERMOCOUPLE CIRCUlT PROOF:
T no = Tu - Tc i
If Te decreases by 10*F, then T o increases by 10*F.
in 350*F + 10*F = 360*F _ - - _ _ _ _ _ - _
USNRC GENERIC panrMTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
13 TOPIC:
-191002 KNOWLEDGE:
Kl.20
. QID:
Plll4
'Which one of the following describes the source of ions collected in a proportional counter (BF detector)?
3 A.
A fraction of the ions created by primary ionizations are collected.
No secondary ionizations take place.
B.
Virtually all of the ions created by primary. ionizations are collected.
No secondary ionizations take place.
C.
Virtually all of the ions created by primary ionizations along with a fraction of the ions created by secondary ionizations are collected.
D.
Virtually all of-the ions created by primary and secondary ionizations are collected.
ANSWER:
D.
QUESTION:
14 TOPIC:
191002 KNOWLEDGE:
Kl.19 QID:
NEW An initial radiation survey is about to be performed in an area of unknown radiation field intensity.
Which one of the following types of radiation monitoring instruments and settings should be used?
A.
A Geiger Mueller survey meter selected to the low range B.
A Geiger Mueller survey meter selected to the high range C.
Jul ion chamber. survey meter selected to the low range D.
Im ion chamber survey meter selected to the high range ANSWER: D.
r 13 -
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOCER 1997 PWR - FORN A 4
QUESTION:
15 TOPIC:
191003 KNOWLEDGE:
K1.02 QID:
P218 An emergency diesel generator (D/G) is operating as the only power source connected to an emergency bus.
The governor of the D/G directly senses D/G and directly adjusts D/G flow to maintain a relatively constant D/G frequency.
A.
speed; fuel B.
speed; air C.
load; fuel D.
load; air ANSWER:
A.
QUESTION:
16 TOPIC:
191003 KNOWLEDGE:
K1.05 QID:
P1618 (Rev)
An air-operated isolation valve requires 2,800 pounds-force (lbf) from its diaphragm actuator and 4 inches of stem travel for proper Operation.
The valve positioner can supply a nominal 117 psig of air pressure to the actuator.
What is the minimum surface area of the actuator diaphragm required for proper valve operation?
A.
24 square inches B.
48 square inches C.
94 square inches D.
138 square inches ANSWER:
A.
PROOF:
F = P A.
A=E=
800 #
2
= 24 i n P
117 #/i n 2 -
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:-
17
-TOPIC:
191003 KNOWLEDGE:
Kl.06 QID:
P2018 A diesel generator is supplying a bus with the governor operating in the isochronous mode.
If a large electrical load on the bus-trips, generator frequency will:
A.
initially increase, and then decrease and stabilize below the initial-value.
B.
initially increase, and then decrease and stabilize at the initial value.
C.
initially increase, and then decrease and stabilize above the initial value.
D.
remain constant during and after load change.
ANSWER:
B.
QUESTION:
lb TOPIC:
191003 KNOWLEDGE:
Kl.08 QID:
P917 Which one of the following Mescribes the response of a direct-acting derivative controller, operating in automatic, to an increase in the controlled parameter above the controller set point?
A.
The controller will develop an output signal that continues to increase until the controlled parameter equals the controller set point, at which time the output signal becomes constant.
B.
The controller will develop an output signal that will remain
.directly proportional to the difference between the controlled parameter and the controller set point.
C.
The controller will-develop an output signal that continues to increase until-the controlled parameter equals the controller set point, at which time the output signal becomes zero.
D. :The controller will develop an output signal that will remain directly proportional to the rate of change of the controlled parameter.
ANSWER:
D.
USNRC GEIMR2ic FUNDAMENTALS EXANINATION OCTOBLA 1997 PWR - FORN A QUESTION:
19 TOPIC:
191003 KNOWLEDGE:
Kl.ll QID:
P19 Why rmast an operator pay particular attention to auto / manual valve controllers placed in the' manual mode?
A.
Manual valve cont.~oller operation can result in excessive valve cycling.
B.
Valve position will no longer automatically change in response to changes in system parameters.
C.
System parameters will no longer automatically change in response to changes in valve position.
D.
The valve can only be operated locally during manual contro11er' operation.
ANSWER: B.
QUESTION:
20 TOPIC:
191004
. KNOWLEDGE:
Kl.07 QID:
P24 Shutting *'te discharge valve on an operating centrifugal pump will cause the motor amps to and the pump discharge pressure to A.
increase, increase B.
decrease, increase C.
increase, decrease D.
decrease, decrease ANSWER:
B.
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOIER 1997 PWR - FORM A QUESTION:
21 TOPIC:
191004 KNOWLEDGE:
K1.04 QID:
P1320 (Rev)
Refer to the drawing of a pump with a recirculation line (see figure below).
Valve "A" will open when pump:
A.
discharge pressure reaches a high set point, B.
discharge pressure reaches a low set point.
C.
flow rate reaches a high set point.
D.
flow rate reaches a low set point.
ANSWER:
D.
A g_;_ _______
T7 8
-. ORIFICE I
"}
O
- DISCHARGE SUCTION PUMP PUMP WITH RECIRCULATION UNE 17 -
USNRC GENERIC FUNDAMENTALS EXAMINATION l
OCTOCER 1997 PWR - FORM A QUESTION:
22 TOPIC:
91004 KNOWLEDGE:
K1.06 QID:
P1221 (Rev)
Refer to the drawing of a cooling water system (see figure below).
The available net positive..iction head for the centrifugal pump will be decreased by:
A.
increasing surge tank level by 5 percent.
B.
throttling heat exchanger cooling water valve "B" more open.
C.
throttling pump discharge valve "C" more closed.
.D.
increasing the heat loads on the cooling water system.
ANSWER: D.
A sqvyt cp s,om ar meue u 1
W
)"
oo=
CE o
PUMP COOLING WATER SYSTEM _
C.
mC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
23 TOPIC:
191004
- KNOWLEDGE:
Kl.09 QID:
NEW
- A-centrifugal _ pump is operating in parallel with a positive displacement pump in an open system.
Each pump has the same
- design pressure.
If pump discharge pressure increases to the maximum design pressure of each pump, the centrifugal pump will be operating at flow and the positive displacement pump will be
?perating at flow.
A.
minimum; minimum B.
minimum; rated C.
rated; minimum D.
rated; rated ANSWER:
B.
QUESTION:
24 TOPIC:
191004 KNOWLEDGE:
K1.15 QID:
P1421 (Rev)
A motor-driven centrifugal pump is operating in an open system with its discharge valve throttled to 50%.
How will the pump be affected if the discharge valve is fully opened?
A.
Motor current decreases and total developed head decreases.
B.
Available net positive suction head (NPSH) decreases, and pump differential pressure decreases.
C.
Total developed head increases and available NPSH decreases.
D.
The potential for pump cavitation decreaseb, and pump differential pressure decreases.
ANSWER:
B. d
l USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOZER 1997 PWR - FORM A QUESTION:
25 TOPIC:
191004 KNOWLEDGE:
K1.12 QID:
P1721 Refer to the drawing of a centrifugal pump operating curve (see figure below).
Which point represents pump operation at runout conditions?
-A.
Point A B.
Point B C.
Point C D.
Point D ANSWER:
C.
POINT A
/
P MP POINT B HMD POINT D POINT C
/.
/
FLOW CENTRlFUGAL PUMe OPERATING CURVE
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997-PNR - FORM A
,c QUESTION:-
'26 TOPIC:
191004 KNOWLEDGE: HK1.21 QID:
P1425 Which one of the following describes the proper location for a
-relief valve that will be used to prevent exceeding the design
~
pressure-of a positive displacement pump and associated piping?
.A.
On the pump suction piping upstream of the suction isolation valve B.
On the pump suction piping downstream of the suction isolation valve C.
.On the pump discharge piping downstream of the discharge ir. elation valve D.
On the pump discharge piping upstream of the discharge isolation valve ANSWER:
D.
QUESTION:
27 TOPIC:
191C05 KNOWLEDGE:
Kl.02 QID:
P528 which one of the following will provide motor protection against electrical damage caused by gradual bearing degradation?
A.
Thermal overload device B.
Overcurrent trip relay C.
Underfrequency relay D.
Undervoltage device-
' ANSWER:
A.
i I
i l
i- '
l i
_USNRC GENERIC FUNDAMENTALS EXAMINATION OCTODER 1997 PWR - FORM A a
QUESTION:
28
. TOPIC:
191005-KNOWLEDGE:
Kl.03
.QID:
P1529 (Rev)
A diesel generator (D/G) is supplying an electrical bus in parallelfwith the grid.
Issuming D/G terminal voltage and bus frequency-do not change, if the D/G governor set point is increased from 60.0 Hz to 60.1 Hz, then D/G'kVAR will
'and D/G amps will' r
A.
remain the same; increase B.
remain the same; remain the same C.
increase; increase
'D.
increase; remain the same ANSWER:
A.
QUESTION:
29 TOPIC:
191005 KNOWLEDGE:
K1.04 QID:
P630 (Rev) i Which one of the following describes the motor current indications that would be observed during the start of a large ac motor-driven centrifugal pump with a closed discharge valve?
A.
Current immediately increases to the full-load value and then decreases to the no-load value over several seconds.
i B.
Current immediately increases to the ne-load value and then stabilizes.
C.
Current immediately increases to greater than the full-load value and then decreases to the no-load value after several seconds.
D.
Current immediately increases to greater than the full-load-value and then decreases to the no-load value after several minutes.
ANSWER:
C.
i l
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
30 TOPIC:
191005 KNOWLEDGE:
Kl.05 QID:
NEW Two identical 4160 Vac induction motors are connected to identical centrifugal pumps being used to provide cooling water-flow in separate systems in a power plant.
Each moter is rated at 1000 hp.
The discharge valve for pump A is fully open and the discharge valve for pump B is fully shut-,
If each motor is then started, the longest time period required-
- to stabilize motor current will be experienced by motor and the-higher stable motor current will be experienced by motor A.
A; A B.
A; D C.
B; A D.
B; B 4
ANSWER:
A.
QUESTION:
31 TOPIC:
191005 KNOWLEDGE:
K1.06 QID:
P1031 The number of starts for an electric motor in a given pe-tod of time should be limited because overheating of the can occur due to the counter electromotive force produced at low rotor speeds.
A.
windings; low B.
windings; high C.
commutator and/or slip rings; low D.
commutator and/or slip rings; high ANSWER:
A..
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTODER 1997-PWR - FORM A
-QUESTION:
32 TOPIC:
191006 KNOWLEDGE:
K1.07 QID:
P1634 (Rev)
Refer to the drawing of a lube oil heat exchanger (see figure below).
Given the-following existing conditions:
th ii
= 1. 8 x 10' lbm/hr 4 e.,
= 3.3 x 10' lbm/hr C..it
= 1.1 Btu /lbm *F p
C,..e., = 1. 0 Btu /lbm *F T o.i.
= 90*F T. ot = 12 0 *F Toit.in = 19 0 *F Tott..oe =?
Which one of the following is the temperature of the oil exiting the heat exchanger (Tott.oot) ?
A.
110*F
.B.
120*F C.
130*F 4
D.
140*F ANSWER:
D.
i
- _p,:.
7 S.f. ;
l uma I
l LtiOE OR,HEATEXCHANGER L !
l USNRC QENERIC FUNDANENTALS EXANINATION OCTO ER 1997 PNR - FORN A PROOF:"
-mc6T
= meat AT
= meat /mc oti Toit.ous
=T oit.t. -(mcaT/nc)
T
= 190 - (3. 3 ) (1. 0) (3 0)-
oia.oo (1. 8) (1.1)
= 140'F QUESTION:
33 TOPIC:
191006 KNOWLEDGE:
Kl.12
- QID:
P32 (Rev)
Refer to the drawing of a lube oil heat exchanger (see figure below).
If deposits accumulate on the outside of the cooling-vater tubes, cooling water outlet temperature will and oil outlet temperature will (Assume oil.and cooling water flow rates remain the same.)
l A.
increase; decrease B.
increase; increase 7
C.
decrease; decrease i
D.
decrease; M_
increase ANSWER:
D.
1 l
1-.
LU8E 0fL EAT EXCHANGER )
i l
USNRC GE3EERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
34 TOPIC:
191006-KNOWLEDGE:
Kl.08 QID:
Pl732 which one of the following will reduce the rate of heat transfer between two' liquids in a heat exchanger? (Assume single-phase
= conditions and a constant specific heat for both liquids.)
A.
The inlet' temperatures of both liquids are decreased by 20*F.
B.
The inlet temperatures of both liquids are increased by 20*F.
C.
The inlet temperature of the hotter liquid is increased by
- 20*F.
D.
The inlet temperature of the colder liquid is increased by 20*F.
J ANSWER:
D.
J 4,
m
USNRC QENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A
' QUESTION:
35 TOPIC:-
191007 KNOWLEDGE:
K1'.01 QID:
Pl736 (Rev)
A_ condensate demineralizer differential. pressure (D/P) gauge indicates 4 psid at 50% flow rate.
Which one of the following combinations of condensate flow and demineralizer D/P observed at various power levels indicates an increase in the accumulation of insoluble corrosion products in the demineralizer?
CONDENSATE DEMINERALIZER FLOW D/P (PSID)
A.
-25%
1.0
- B.
60%
6.0 C.
75%
9.0 D.
100%
15.0 4
ANSWER:
B.
PROOF:
F = N; H a-Na H /Ha = (F /F )2 3
2 2
Ha = H (F /F )8 2
2 025% flow, D/P should be 1.0 psid 060% flow, D/P should be 5.76 psid 075%. flow, D/P should be 9.0 psid 0100% flow, D/P should be 16.0 psid Only choice B exceeds the expected D/P.
T 4
N 27 -
~-
i..
USNRC GENERIC FUNDA3GNTALS EXAMINATION i
OCTOCER 1997 PWR - FORM A
~
QUESTION:
36' TOPIC:
191007 KNOWLEDGE:.Kl.03 QID:
P936 (Rev)
To determine the demineralization factor for a demineralizer, the parameters that must be monitored are inlet and outlet A.
pH B.
conductivity C.
suspended solids D.
pressure ANSWER:
B.
QUESTION:
37 2
TOPIC:
191007 KNOWLEDGE:
Kl.14 QID:
P1335 The plant is operating at 70% stable power level when the temperature of reactor coolant letdown passing through a boron-saturated mixed bed ion exchanger is increased by 20*F.
As a result, the boron concentraticn in the effluent of the ion exchanger will because the affinity of the ion exchanger for boron atoms has A.
decrease; decreased B.
-decrease; increased C.
increase; decreased D.
increase; increased ANSWER:
C. --
USNRC GENERIC FUNDARGDITALS EXANINATION -
OCTO ER 1997 PWR - FORN A QUESTION:
38 TOPIC:
191008 KNOWLEDGE:- Kl.04 QID:
P2041 Two identical 1000 Mw electrical generators are operating in parallel supplying.the same electrical bus.
The generator output breakers also provide identical protection for the generators.
Generator A and B output indications are as follows:
Generator A Generator B 416C Volts 4160 Volts 60.2' Hertz 60.2 Hertz 50 Mw 100 Mw 25 MVAR (out) 50 MVAR (out)
A malfunction causes the voltage regulator setpoint for generator B to slowly increase continuously toward a maximum o; 4400 volts.
If no operator action is taken, which one of the following describes the current indications for generator A?
A.
Current will decrease continuously until the output breaker for generator B trips on reverse power.
B.
Current will decrease continuously until the output breaker for generator A trips on reverse power.
C.
Current will initially decrease, and then increase until the output breaker for generator B trips on overcurrent.
D.
Current will initially decrease, and then increase until the output breaker for generator A trips on overcurrent.
ANSWER: C.
USNRC GENERIC FUNDMENTALS EXANINATION j
OCTO ER 1997 PWR - FORN A 4
QUESTION:
39 j
TOPIC:
191008 1
KNOWLEDGE:
Kl.06 QID:
Pl739 (Rev)
]
Refer to the drawing of a valve motor control circuit (see figure below) for a valve that is currently fully open.
Which one of the following~ describes the valve response if the control switch is taken to the "Close" position for two seconds and then released?
A.
The valve will not move.
B.
The valve will close fully.
C.
The valve will begin to close and then stop moving.
D.
The valve will begin to close and then open fully.
ANSWER:
C.
+125 VDC Neutral Neutral
% n.=,.i
% man.
O O
O
,,, p,,,,,,,,,,Q,,,
O (R)
(G)
Ki 2_
0;wn Close Open Close 2
Alarm T
131
_lm
_Im
_Ls4
_tss
~
~
m~ ~open he~" ope m
~~
~" ope m ope we op vet = rosy open vain remy o sed v.sw remy Vain Feay Valw Feay K21 K11 opes N
opes l
-A
-A 4-4-
K1 K2 125vnc VALVE MOTOR CONTROL CIRCLIT !
. _ ~
USNRC GENERIC. FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORN A-QUESTION: _
40 TOPIC:
191008 KNOWLEDGE:
K1.08 QID:
P1842 (Rev)
A main generator is being prepared for paralleling with the grid.
Which one of the following indicates that the main generator and
- grid-voltages are in phase?
A.
The voltage of the' generator is equal to the voltage of the-grid.
B.
The frequency of the generator is equal to the frequency of the grid.
~
.The synchroscope is turning slowly in the clockwise C.
direction.
D.
The synchroscope is passing through the 12 o' clock position.
ANSWER:
D.
QUESTION:
41 TOPIC:
191008 KNOWLEDGE:
Kl.08 QID:
P2040 A main generator is being prepared for paralleling with the grid.
Which one of the following conditions will cause the main generator to immediately supply reactive power (MVAR) to the grid when the generator output breaker is closed?
I A.
Generator voltage is 1% higher than grid voltage.
B.
Generator voltage is 1% lower than grid voltage.
C.
The synchroscope is turning slowly in the clockwise L
direction.
D.
The synchroscope is turning slowly in the counterclockwise direction.
i ANSWER:
A.
L l-
- _ = _. -.
USNRC GENERIC FU3mmnTALS EXAMINATION OCTO2ER 1997 PNR - FORN A QUESTION:
42.
TOPIC:-
191008
. KNOWLEDGE:
Kl.11 QID:
P1932-While remotely investigating the condition of a normally-open motor control center (MCC) feeder breaker, an operator observes the following indications:.
Green breaker position indicating light is out.
Red breaker position indicating light is lit.
MCC voltmeter indicates normal voltage.
MCC ammeter indicates zero amperes.
Based on these indications, the operator should report that the circuit breaker is and racked A.
open; in B.
closed; in i
C.
open; to the test position D.
closed; to the test position ANSWER:
8.
QUESTION:
43 TOPIC:
191008 KNOWLEDGE:
Kl.10 QID:
P943
-What is an advantage of using high voltage electrical disconnects instead of circuit breakers to isolate main power transformers?
A.
Disconnects provide positive visual indication that the circuit is broken.
B.
Disconnects can be operated either locally or remotely.
C.
Disconnects are cheaper and provide the same protection as a breaker.
D.-
Disconnects are capable of passing a higher current with less heating than a breaker.
' ANSWER:
A......
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTO ER 1997 PWR - FORM A
. QUESTION:
44
. TOPIC:
191008 KNOWLEDGE:
K1.08 QID:
P2044 (Rev)
'An isolated electrical bus is being supplied by generator A.
Generator B is about 'o be connected to the same electrical bus.
c Generators A and B are both rated at 1000 Mw.
Generator A and B output indications are as follows:
Generator A Generator B 4140 Volts (160 Volts 60.8 Hertz 60.2 Hert:
25Mw 0 Mw 10-MVAR 0 MVAR When the output breaker for generator B is closed, which generator.is more likely to trip on reverse power?
A.
Generator A due to the lower initial voltage B.
Generator A due to the higher initial frequency C.
Generator B due to the higher initial voltage D.
Generator B due to the lower initial frequency ANSWER:
D.
t t,
e--
4 USNRC GENERIC FUNDAlptNTALS EXANINATION OCTOBER 1997-PWR - FORN A 4
QUESTION:
45 TOPIC:
192001 KNOWLEDGE:
Kl~.02 OID:
P1245-As compared to a prompt neutron, a delayed neutron, born from.the-same fission event, is more likely to:
A.
leak out of the core.
B.-
be absorbed in the-moderator.
1 C.
be captured by a U-238 nucleus.
D.
cause fission of a U-235 nucleus.
.ANSWSR:
D.
j_
i_
i.
i L
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 FNR - FORM A
- QUE!, TION :
46
-TO"IC:
192002
-KNOWLEDGE:
K1.13 QID:
P1446 A reactor;at the beginning of core life has-been shut.down from 100% power and_ cooled down to 340*F over three days.
During the cooldown, boron concentration was increased by 200 ppm.
Given the following absolute values of reactivities added during the shutdown and cooldown, assign a-(+) or (-) as appropriate and choose the current value cf shutdown margin.
( ) 3.0% AK/K Xenon c.
= ( ) 3.5% AK/K Power defect = ( ) 4.0% AK/K Rods
=( ) 7.0%_AK/K Cooldown.
( ) 2.0% AK/K
=
A.
-1.5% aK/K B.
-2.5% AK/K C.
-7.5% AK/K D.
-9.5% AK/K ANSWER:
A.
PROOF:
g Xenon
(+) 3.0% ok/k
=
(-) 3.5% ak/k
=
Power D
(+) 4.0% Ak/k
=
Rods
(-) 7.0% ak/k
=
Cooldown = (+) 2.0% ak/k SDM
=
(-) 1.5% Ak/k l.
t
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
47 TOPIC:
192002
' KNOWLEDGE:
K1.14
.QID:
NEW A reactor is operating at 80% power when the-operator adds-10 gallons of boric acid to the-reactor coolant system (RCS).
Over the next several minutes, the operator adjusts control rod position as necessary to maintain a constant reactor coolant average temperature.
When the plant stabilizes, shutdown margin will be and axial power distribution will have shifted toward the of the core.
A.
the same; top B.
the same; bottom C.
larger; top D.
larger; bottom ANSWER: C.
I l
i 1
i i
USNRC GENERIC FUNDADGNTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
48 TOPIC:
192003 KNOWLEDGE:
K1.01 QID:
NEW Two reactors are currently shut down with a reactor startup in-progress. The two reactors are identical-except that reactor A has a source neutron' strength of 100 neutrons per second and reactor B source neutron strength is 200 neutrons per second.
Control rods are stationary and Keff is 0.98 in both reactors.
Core neutron level has. reached equilibrium-in both reactors.
Which one of the following lists the core neutron level (neutrons per second) in reactors A and B?
Reactor A Reactor _B A.
5,000 10,000 B.
10,000 20,000 C.
10,000 40,000 D.
20,000 40,000 ANSWER:
A.
PROOF:
CRun = S/(1-K)
Reactor A CRun = 100/.02
= 5,000 Reactor B CRsio = 2 00 /. 02
= 10,000; -
l USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
49 TOPIC:
192003 KNOWLEDGE:
Kl.07 QID:
NEW Which one of the following percentages of fuel undergoing fission in a reactor will result in the largest reactor core effective delayed neutron fraction?
90%
7%
3%
B.
80%
6%
14%
C.
70%
23%
D.
60%
6%
34%
ANSWER:
A.
Of:lESTION:
50 TOPIC:
192004 l'.NOWLEDGE :
Kl.03 QID:
P251 Under which one of the following conditions is a reactor core most likely to have a positive moderator temperature coefficient?
A.
High coolant temperature at beginning-of-life B.
High coolant temperature at end-of-life C.
Low coolant temperature at beginning-of-life D.
Low coolant temperature at end-of-life ANSWER: C.,
1
m..... _ _ _. _. _ _ _.. _ _ _ _ _ _. _ _ _ _. _
USNRC GENERIC FUNDMO9fTALS EXAMINATIO0f OCTOBER 1997 PWR - FORN A i
i QUESTION.
51 TOPIC:
192004 KNOWLEDGE:
Kl.05 QID:
P1650 (Rev)
Which one of the following pairs of isotopes is responsible for the negative reactivity associated with a fuel temperature i
increase near the end of core life?
A.
U-235 and Pu-239-B.
U-235 and Pu-240 C.
D.
U-238 and Pu-240 ANSWER: D.
P QUESTION:
52 TOPIC:
192004 KNOWLEDGE:
K1.07 QID:
P1951 A reactor is operating at 70% power.
Which one of the following will directly result in a less negative fe,1 temperature coefficient?
(Consider only the effect or the change in each listed parameter.)
A.
Increase in fuel temperature B.
Increase in moderator temperature C.
Increase in moderator voids D.
Increase in Pu-240 inventory 114 the core ANSWER:
A.
l
{
USNRC GENMRIC FUNDAMENTALS EXAMINAT'.ON OCTOBER 1997 PWR - FORM A QUESTION:
53 TOPIC:
192004 KNOWLEDGE:
Kl.11 QID:
P351 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 acid required to increase boron concentration by 50 ppm at EOL (100 ppm).
A.
the same
~
B.
four times as large C.
eight times as large D.
twelve times as large ANSWER:
A.
QUESTION:
54 TOPIC:
192005 KNOWLEDGE:
Kl.07 QID:
P2156 (Rev)
Which one of the following events will cause control rod worth to decrease?
A.
Fuel temperature decreases as the fuel pellets come into contact with the fuel clad.
B.
RCS boron concentration increases by 5 ppm at 80% power with no rod motion.
C.
Reactor power is decreased from 100% to 90% with no rod motion.
D.
Early in core life, the concentration of burnable poison decreases.
ANSWER: B. _ _ _ - _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _.
USSDLC GENERIC FUIREMENTALS EXAMINATION i
OCTOBER 1997 PWR - FORM A i
QUESTION:
55 TOPIC:
192005 KNOWLEDGE:
K1.05 QID -
P1471 (Rev)
The reactor is operating at steady state 70% power with the following conditions:
600 ppm Contral rod position:
110 inches RCS average temperature:
575'F Reactor power is increased to 100% over the next four hours.
The 100% reactor power conditions are as-follows:
590 ppm Control rod pocition:
130 inches RCS average temperature:
580*F Given the following reactivity coefficient / worth values, and neglecting fission product poison reactivity enanges, what is the differuntial control rod worth?
Power coefficient:
-0.3% AK/K/%
Hoderator temperature coefficient:
-0.2% AK/K/*F Differential boron worth:
-0.1% AK/K/ ppm A.-
0.2% AK/K/ inch B.
0..15% AK/K/ inch C.
0.4% AK/K/ inch D.
0.5% AK/K/ inch ANSWER: C..
PROOF:
pg = 30 x -0.3 = -9.0% ak/k p, = -10 x -0.1 = +1. 0% ak/k pn + p. = -9. 0 + 1. 0 =
-8. 0% ok/k CRW = p added/ inches = +8.0/20 = +0.4% ok/k/ inch
, f u
USHRC GENERIC FUNDAMBfTALS EXAMINATION OCTOBER 1997 FHR - FORN A QUESTION:
56
' TOPIC:
192005 l
KNOWLEDGE:
Kl.10 QID:
P455 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% 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 Core.
C.
The fuel loading in the lower half of the core contains a higher U-235 enrichment.
D.
The moderator temperature coefficient of reactivity is adding less negative reactivity in the lower half of the core.
ANSWER:
D.
1 1
QUESTION:
57 TOPIC:
192005 KNOWLEDGE:
Kl.16 QID:
P1657 (Rev)
A reactor is operating at 85% power with all control rods fully wi.thdrawn.
Assuming reactor power does not change, which one of the following compares the effects of partially inserting (50%) a single center control rod to the effects of dropping (full insertion) the same control rod?
A.
A partially inserted rod causes a smaller change in axial
. power distribution.
B.
A partially inserted rod causes a smaller-change in radial power distribution.
C.
A partially inserted rod causes a greater change in shutdown margin.
D.
A partially inserted rod causes a smaller' change in shutdown margin.
ANSWER:
B.
e..
. ~ _ - - - - _. _ -.._-...... --.......--
USNRC GEHF'AIC FtP m M ALS EXAMINATION OCMBER 1997 PWR - FORM A QUESTION:
58 TOPIC:
19200G KNOWLEDGE:
Kl.06 QID:
P2060 A reactor is initially operating at 50% powe.i with equilibrium core xenon-135.
Power is increased to 100% over a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period and average reactor coolant temperature is adjusted to 588'F 1
using manual rod control.
Rod control is left in Manual and no subsequent operator actions are taken.
w I
considering only the reactivity effects of core xenon-135 changes, which one of the following describes the average reactor coolant temperature 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the power change?
A.
Greater than 588'F and decreasing slowly B.
Greater than 588'F and increasing slowly C.
Less than 588'F and decreasing slowly D.
Less than 588'F and increasing slowly ANSWER:
A.
t QUESTION:
59 TOPIC:
192006 KNOWLEDGE:
Kl.07 QID:
P1561 Which one of the following reactor prescram conditions requires the least amount of control rod withdrawal to attain reactor criticality during peak core xenon conditions after a reactor scram from equilibrium core xenon conditions?
4 A.
Beginning of core life (BOL) and 100% power B.
End of core life (EOL) and 100% power C.
BOL and 20% power D.
EOL and 20% power ANSWER:
C.
l l
l L -
g 4
is,mer 9
o
-r.
.-4.w-g
.'i wr.=wi.'-.
m w
USNRC nerelLIC FUNDMEENTALS EXANINATION OCTOBER 1997 PWR - FORN A QUESTION:
60 TOPIC:
192006 i
KNOWLEDGE:
Kl.09 QID:
PS61 (Rev)
A reactor is initially shut down with no xenon in the core.
The
- reactor is brought critical and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later power level is at j
the point of adding heat.
The shift supervisor has directed that power be maintained constant-at this level for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> fur testing.
To accomplish this, control rods will have to be:
- A.
withdrawn periodically for the duration of the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
B.
inserted periodically for the duration'of the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
C.
withdrawn periodically for 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, then inserted periodically.
D.
inserted periodically for 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, then withdrawn periodically.
i AMSWER:
A.
4 QUESTION:
61 TOPIC:
192006 KNOWLEDGE:
Kl.11 QID:
P659 (Rev)
A reactor has been operating at steady-state 50% power for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following a one-hour power reduction from steady-state 100%
power.
Which one of the following describes the current core xenon-135 concentration?
A.
Increasing toward a peak B.
Decreasing toward an upturn C.
Increasing toward equilibrium D.
Decreasing toward equilibrium ANSWER: D.
l 44 -
j E'y r-
-N
.a y
>i aa w.
y v.
iy yn-.~a
l*
USNRC QENERI'* FUNDAMENTALS EXAMINATION OCTOBER is97 PWR - FORN A 4
QUESTION:
62 TOPIC:
192006 KNOWLEDGE:
Kl.12 QID:
P1063 (Rev)
Eighteen hours after a reactor trip from 100% power, equilibrium xenon conditions, the amount of core xenon will be:
A.
lower than 100% equilibrium xenon, and will have added a net positive reactivity since the trip.
B.
Jower than 100% equilibrium xenon, and will have added a net negative reactivity since the trip.
C.
higher than 100% equilibrium xenon, and will have added a not positive reactivity since the trip.
D.
higher than 100% equilibrium xenon, and will have added a net negative reactivity since the trip.
ANSWER:
D.
QUESTION:
63 TOPIC:
192006 KNOWLEDGE:
Kl.14 OID:
P1762 A reactor startup is being conducted and criticality has been achieved 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after a reactor scram from long term operation at full power.
After 1 additional hour, reactor power is stabilized at 10-'% power and all control rod motion is stopped.
Which one of the following describes the response of reactor power over the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> without any further operator actions?
A.
Power increases toward the point of adding heat due to the decay of Xe-1?5.
B.
Power increases toward the point of adding heat due to the decay of Sm-149.
C.
Power decreases toward the shutdown neutron level due to the buildup of Xe-135.
D.
Power decreases toward the shutdown neutron level due to the buildup of Sm-149.
ANSWER:
A. ___
USNRC GENERIC FUNDAMENTALS EXAMINATIOtt-OCTOBER 1997 PWR - FORN A s
QUESTION:
64 TOPIC:
192007 KNOWLEDGE:
K1.05 QID:
P1964 Which one of the following compares the rate at which reactor.
power can be increased at the beginning of core life (BOL) to the end of core life (EOL)?
i A.
Faster at EOL due to faster changes in boron concentration
~
i B.
Faster at EOL due to greater control rod worth C.
Faster at BOL due to faster changes in boron concentration D.
Faster at BOL due to greater control rod worth ANSWER:
C.
i s
i 1
4 46 -
I USSIRC GENERIC Ft2RNWEENTALS EXAMINATIO8f OCTOBER 1997 PWR - FORM A QUESTION:
65 TOPIC:
192008 KNOWLEDGE:
K1.04 QID:
P1972 (Rev) l During a reactor startup, source range indication is stable at 100 cps with K.r, at 0.95.
After a number of rods have been j
withdrawn, source range indication stabilizes at 270 cps.
Which one of the following is the new Kerr?
A.
0.936 B.
0.972 C.
0.981 D.
0.990 ANSWER: C.
PROOF:
CR (1-K ) = CR 2
3 2 (1-Ka )
CR /CR (1-K ) / (1-K )
=
2 3
270/100 = 0.05/1-K 1-K = 0.05/2.7 1-0.0185 K
=
0.98148 K
=
4 b
l E..
er-p u-W mp
-wv
+
n F
9v=P---
er--
-t-s-
- - =
---w'ar ap
-
- ween m
t USMAC GENERIC FUNDAMENTALS EXANINATION OCTOBER 1997 PNR - FORN A 4
QUESTION:
66 TOPIC:
192008 KNOWLEDGE:
Kl.07 QID:
P1666 An estimated critical rod position (ECP) has been calculated for a reactor startup r.) be performed 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after a reactor trip that ended three months operation at 100% power.
1 Which one of the following conditions will result in criticality occurring at a lower than estimated critical ~' rod position?
-A.-
Adjusting reactor coolant system boron concentration to 50 ppm higher than assumed for startup calculations B.
A malfunction resulting in control rod speed being slower than normal speed C.
Moving the time of startup from 15 hour1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />
.s
' hours following the trip D.
Using a pretrip reactor power of 90% to determine power defect ANSWER:
D.
QUESTION:-
67 TOPIC:
192008 KNOWLEDGE:
Kl.09 QID:
P68 (Rev)
When a reactor is exactly critical, reactivity is:
A.
infinity.
B.
undefined.
C.
0.0 AK/K.
D.
1.0 AK/K.
ANSWER:
C.
~.. _.. - _. _ _. -. -. -. - - -. -.
USMRC CE:8ERIC FUlmhatENTALS EXAMIIIATION OCTOBER 1997 PWR - FORM A QUESTION:
68 TOPIC:
192008 KNOWLEDGE:
K1.10 QID:
P1567 with a reactor on a constant period of 30 minutes, which one of the following power changes requires the least time to occur?
A.
1% power to 6% power B.
10% power to 20% power C.
20% power to 35% power D.
40% power to 60% power ANSWER:
D.
e" t
PROOF:
Pr = Po tln Pr/P = t in 6/1(30) = 1.79(30) = t = 53.7 minutes
.693(30) = t = 20.8 minutes in 20/10(30)
=
in 35/20(30)
.56(30) = t = 16.8 minutes
=
In 60/40(30)
.41(30) = t = 12.3 minutes
=
4 s _
USNRC GENERIC FUNDAMENTALS E4 AMINATION OCTOBER 1997 PNR - FORM A e
QUESTION:
69 TOPIC:
192008 KNOWLEDGE:
Kl.14 QID:
P972 (Rev)
A reactor is critical at the point of adding heat (POAH) when a small amount of negative reactivity is added to the core.
If the j
same amount of positive reactivity is added to the core approximately 5 minutes later, reactor power will A.
increase ar.d stabilize at the POAH.
B.
quickly stabilize at a power level below the POAH.
C.
continue to decrease on a negative 80 second period until the shutdown equilibrium neutron level is reached.
D.
continue to decrease with an unknown period until the shutdown equilibrium-neutron lovel is reached.
' ANSWER:
B.
QUESTION:
70 TOPIC:
192008 KNOWLEDGE:
Kl.21 QID:
P1370 A reactor has been operating at 80% power for several weeks.
A partial steam line break occurs and 2% total steam flow is escaping.
Turbine load and control rod position remain the same.
Assuming no operator or automatic actions, when the plant stabilizes, reactor power will be and average reactor coolant temperature will be A.-
higher; higher B.
unchanged; higher C.
higher; lower-l D.
unchanged; Jower ANSWER:
C.
50 -
- -.., -. ~.
USNRC GENERIC FUNDAMEINTALS EXAMINATIOtt i
OCTOBER 1997 PWR - FORN A 4
QUESTION:
71 TOPIC:
192008 KNOdLEDGE:
Kl.26 QID:
P370 After one month of operation at 100% reactor power, the fraction of thermal power being produced from the decay of fission products in the operating reactor-is:
A.
greater than 10%.
B.
greater than 5% but less than 10%.
C.
greater than 1% but less than 5%.
D.
less than 1%.
ANSWER:
B.
QUESTION:
72 TOPIC:
192008 KNOWLEDGE:
K1.27 QID:
P1672 (Rev)
A reactor is operating at 100% power near the end of core life.
The greatest contribution to core heat production is being provided by the fission of:
A.
B.-
l C.
D.
U-238 and Pu-241.
ANSWER:
B..,
i USNRC GENERIC FUNDMEENTALS EXANINATION l
OCTOBER 1997 PNR - FORN A i
4 QUESTION:
73 TOPIC:
193001 l
KNOWLEDGE:
K1.01 OID:
P2073 (Rev)
Which one of the following is arranged from the highest pressure to the lowest pressure?
4 A.-
2 psig, 12 inches Hg absolute, 8 psia B.'
2 psig, 18 inches hg absoluto, 8 psia 1
C.
12 psia, 20. inches Hg absolute, 2 psig D.
12 psia, 30 inches Hg absolute, 2 psig ANSWER:
B.
PROOF:
A.
is equivalent to 17 psia, 6 psia, 8 psia B.
is equivalent to 17 psia, 9 psia, 8 psia C.
is equivalent to 12 psia, 10' psia, 17 psia D.
is equivalent to 12 psia, 15 psia, 17 psia QUESTION:
74 TOPIC:
193003 J
KKJWLEDGE:
K1.14 QID:
P1674 Y
A reactor trip occurred 10 minutes ago due to a loss of coolant accident.
Emergency coolant injection is in progress and j
pressurizer level is increasing.
Current pressurizer conditions are as follows:
i Pressurizer liquid temperature = 540*F Pressurizer vapor temperature
= 607'F Pressurizer pressure
= 1410 psia Pressurizer level
= 60%
Given these conditions, the pressurizer liquid is and the pressurizer vapor is A.
saturated; saturated B.
saturated; superheated C,
subcooled; saturated D'
subcooled; superheated n
ANSWEP.:
D.
52 --
i
-y
.,s.
v 4,
,. +,, -,.
m
l*
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBEh 1997 PWR - FORM A QUESTION:
75 TOPIC:
193003 KNOWLEDGE:
K1.25 QID:
NEW 1 x 10' lbm/hr saturated steam at 30% steam quality is leaving a main turbine and entering a condenser at 2.0 psia.
Condensate is entering the hotwell at 118 degrees F.
Which one of the following is the approximate condenser heat transfer rate?
A.
3.1 x 10' Btu /hr s
B.
5.8 x lo Btu /hr C.
7.2 x 10' Btu /hr D.
9.9 x 10' Btu /hr ANSWER:
A.
PROOF:
From steam tables:
Exhaust steam enthalpy is 1116.1 -
(0.7)(1022.2) = 400.56 Btu /lbm From steam tables:
Condensate enthalpy is 86 Btu /lbm Q = m-dor delta-h Q = (1,000,000 lbm/hr) (400. 6 - 86 Btu /lbm)
Q = 314,600,000 Btu /hr QUESTION:
76 TOPIC:
193004 KNOWLEDGE:
Kl.11 QID:
P1176 (Rev)
The thermodynamic cycle efficiency of a power plant will increase if:
A.
the amount of condensate depression is decreased.
B.
a high-pressure feed water heater is removed from service.
C.
condenser vacuum decreases from 29 inches to 25 inches.
D.
power is decreased from 100% to 25%.
ANSWER:
A. __
USNRC GENERIC FUNDAMENTALS EXAMINATION i
OCTOBER 1997 MTR - FORN A a
QUESTION:
77 TOPIC:-
193004 KNOWLEDGE:
Kl.15 l
QID:
P1277 l
A heatup and pressurization of the reactor coolant system (RCS) is in progress following a maintenance shutdown.
RCS pressure is i
800 psia =with a steam bubble in the pressurizer.
Pressurizer power-operated relief valve (PORV) tailpipe temperature has been steadily rising.
Assume 97.5% quclity saturated steam in the pressurizer vapor space, PORV downstream pressure is 30 psia, and PORV leakage-is an ideal throttling process.
Which one of the following is the expected PORV tailpipe temperature if a PORV is leaking by?
A.
264*F B.
284*F C.
302*F D.
322*F ANSWER:
B.
F QUESTION:
78 TOPIC:
193005 KNOWLEDGE:
Kl.03 QID:
P277 (Rev)
If the moisture content of the steam supplied to a main turbine increases, turbine work will:
A.
decrease because the enthalpy of the ceam being supplied to the turbine has decreased.
B.
decrease because moist steam results in more windage losses in the turbine.
C.
increase because the enthalpy of the steam being supplied to the turbine has increased.
l-D.- -increase because moist steam results in less-windage losses
.in the turbine.
I' ANSWER: A.
i l L ll
.. -=
USNRC GENERIC FUNDhMI3fTALS EXAMINATION OCTOBER'1997 PNR - FORM A QUESTION:-
79 TOPIC:
193006 KNOWLEDGE:
K1.04 QID:
P78 (Rev)
Which one of the following operating practices minimizes the possibility of water hammer?
A.
Change valve positions as rapidly as possible.
t B.
Start centrifugal pumps with the discharge valve throttled.
C.
Start positive displacement pumps with the discharge valve closed.
D.
Vent systems only after initiating system flow.
ANSWER:
B.
l QUESTION:
80 TOPIC:
193006 KNOWLEDGE:
Kl.05 QID:
P1986 A 47 gpm leak has developed in a cooling water system that is operating at 150 psig.
Which one of the following will be the leak rate when system pressure has decreased to 75 psig?
A.
23.5 gpm B.
33.2 gpm C.
36.5 gpm D.
37.3 gpm ANSWER:
B.
PROOF:
DP ' = f 2
( f:/ f a)'
DP /DP:
=
3 l.414 = 47/f f = 47/1.414 f: = 33.2 gpm _.,
USMRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PNR - FORM A l
QUESTION:
81~
i TOPIC:
193006 KNOWLEDGE:
K1.11 OID:
P1582 Refer to the drawing of a cooling water system in which only pump A is operating and the pump discharge valve is currently 50% open (see figure below).
If pump A is cavitating, which one of the following will reduce i
or eliminate cavitation in pump A7 A.
Starting pump B B.
Positioning the discharge valve to 75% open C.
Raising the water level in the surge tank by 2 feet
-D.
Decreasing heat exchanger service water flow rate by 10%
ANSWER:
C.
P T.T n##o.
=:
-m LOADS U A R i;4
^o PUMP A PUMPB COOLING WATER SYSTEM 56 -
USNRC GENERIC FUNDAMENTALS EXAMINATION-OCTOBER 1997 PWR - FORM A QUESTInN:
82 SOPIC:
193006 KNOWLEDGE:
K1.15 QID:
NEW Water at 90 degrees F and 50 psig is flowing through a 10-inch diameter pipe at 100 lbm/sec.
The pipe then splits into two pipes, a 4-inch diameter pipe and an 8-inch di:<eter pipe.
Disregarding any flow restrictions other than pipe size, which one of the following lists the approximate flow rates through the 4-inch and 8-inch diameter pipes?
4-inch Pipe 8-inch Pipe (1bm/sec)
Jibm/sec)
A.
20 80 B.
25 75 C.
30 70 D.
33 67 l
ANSWER:
A.
PROOF:
m = pAv mi + m2 = 100 pAiv + pA2v = 100 pv(Al +A2) = 100 pv(80) = 100 pv = 100/80 ml = pvAl ml = 100/80 (16) ml = 1600/80 = 20 lbm/sec m2 = pvA2 m2 = 100/80 (64) mi_= 6400/80 = 80 lbm/sec i.
l.
! L
..r
~ _ - =. - - - -
USNRC GENERIC FUNDANENTALS EXAMINATION OCTCBER 1997 PNR - FORN A QUESTION:
83 TOPIC:
193006 KNOWLEDGE:
Kl.15 QID:
P1282 Two centrifugal pumps and two positive displacement pumps are able to be cross connected to provide flow in a system.
Each pump will produce 100 gpm at 1000 psig discharge pressure and each pump has a design maximum pressure of 1500 psig.
If 'fatem pressure is 1200 psig, which one of the following will p'
ce the graatest system flow rate?
A.
Two positive displacement pumps in series B.
Two positive displacement pumps in parallel C.
Two centrifugal pumps in series D.
Two centrifugal pumps in parallel ANSWER:
B.
QUESTION:
84 TOPIC:
193007 KNOWLEDGE:
K1.01 QID:
NEW Which one of the following dercribes a heat transfer process in which convection is the most significant heat transfer mechanism?
A.
From the reactor fuel to the core barrel during core uncovery B.
Through.the tube walls in a steam generator during normal operation at 100% power C.
From the reactor fuel to the steam generators during a station. blackout D.-
From fuel pellet centerline to fuel clad during normal operation at 100% power ANSWER:
C..
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORN A QUESTION:
85 TOPIC:
193007 KNOWLEDGE:
Kl.06 QID:
P384 The power range nuclear instruments have been adjusted to 100%
based on a calculated calorimetric (secondary heat balance).
Which one of the following will result in actual reactor power being less than indicated reactor power?
A.
The feedwater temperature used in the calorimetric calculation is higher than actual feedwater temperature.
B.
The reactor coolant pump heat input term is omitted from the calorimetric calculation.
C.
The feedwater flow rate used in the calorimetric calculation is lower than actual feedwater flow rate.
D.
The steam pressure uq ni in the calorimetric calculation is higher than actual steam pressure.
ANSWER:
B.
i
- '59 -
______._____m.___-_______
USNRC GENERIC FUNDAMEBrrALO EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
86 TOPIC:
193008 KNOWLEDGE:
K1.01
-QID:
P1286 Refer to the drawing of a pool boiling curve (see figure below).
Which region of the curve contains the operating point at which the hottest locations of the reactor operate to transfer heat from the cladding to the coolant at 100% power?
)
A.
Region I B.
Region II C.
Region III D.
Region IV ANSWER:
B.
I ll lil '
IV i
Loo HEAT FLUX log AT POOL BOILING CURVE
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 FWR - FORM A QUESTION:
87 TOPIC:
193008 KNOWLEDGE:
Kl.03 QID:
P487 (Rev) i Which one of the following describes why the core heat transfer rate increases when nucleate boiling begins on the surface of a i
fuol rod?
A.
Steam has a greater thermal conductivity than water.
B.
The aormation of steam bubbles increases coolant flow rate along the fuel rod.
C.
Radiative heat transfer begins to supplement convective heat 7
transfer.
D.
Heat transfer by steam bubble formation is more effective than through a liquid film.
ANSWER:
D.
QUESTION:
88 TOPIC:
193008 KNOWLEDGE:
Kl.05 QID:
P1889 (Rev)
A plant is operating with the following initial conditions:
Reactor power is 55% in the middle of a fuel cycle.
Axial and radial power distributions are peaked in the center of the core.
Which one of the following will decrease the steady-state departure from nucleate boiling ratio?
A.
A reactor trip occurs and one control rod remains fully withdrawn from the core.
B.
A pressurizer malfunction increases reactor coolant system pressure by 20 psig.
C.
The operator increases reactor coolant boron concentration by 5 ppm with no rod motion.
D.
Core Xe-135 depletes in proportion to the axial and radial power distribution with no rod motion.
ANSWER:
D..
USNRC GENERIC FUNDAMENTI.LS EXANINATION OCTOBER 1997 PWR - FORN A QUESTION:
89 TOPIC:
193000 KNOWLEDGE:
K1.07 QID:
P1689 (Rev)
Refer to the drawing of a pool-boiling curve (see figure below).
The point at which heat flux stops increasing and the critical heat flux has been reached (point B), marks ~the beginning of:
A.-
nucleate boiling.
B.
stable film boiling.
-C.. partial film boiling.
D.
single-phase convection.
ANSWER:
C.
3 I
l l
3 l
1 8
D LOO HEAT FLUX LOG AT POOL 90 lung CURVE 62 -
USNRC GENERIC FUltDAMENTALS EXAMINATION OCTOBER 1997 PNR - FORM A QUESTION:
90 TOPIC:
193008 KNOWLEDGE:
Kl.10 QID:'
P990 A reactor is operating at 100% steady-state power at the end of core life with all control rods fully withdrawn.
At what axial location in a typical fuel assembly will the m_inimum departure from nucleate boiling ratio occur?
A.
At the bottom of the fuel assembly B.
At the top of the fuel assembly C.
Between the bottom and the midplane of the fuel assembly D.
Between the midplane and the top of the fuel assembly ANSWER:
D.
QUESTION:
91 TOPIC:
193008 KNOWLEDGE:
K1.19 QID:
P1886 (Rev)
A reactor is producing 3400 MW of thermal output with a vessel AT of 60*F and a vessel mass flow rate of 1.1 x 10' lbm/hr.
If core AT is 63.6*F,. what is core bypass flow rate?
(Assume bypass flow AT equals 0*F.)
A.
- 5. 66 x 10' lbm/hr B.
6.23 x 10' lbm/hr C.
- 5. 66 x 10' lbm/hr D.
6 23 x 10' lbm/hr_
ANSWER:
B. <
____.m.__
i USHRC GENERIC FUNDAMENTALS NJtANINATION OCTOCER 1997 PWR - FORM A 1
PROOF:
D = icp AT (c p AT, = (c p AT, + %c p AT, AT' 60 '
8 4=4
= 1.1 x 10 #/ hr AT, 63.6 t
3 4 = 1.1(. 9434) x 10 #/ hr = 1. 038 x 10' #/ hr 8
4 = h. + %
I
%=4-4
= ( 1.1 - 1. 032) x 10' #/ hr 1
= 0. 0623 x 10' #/ hr
= 6. 23 x 10' #/ hr l
1 4
4 a
i b -.
,,. _.J
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PNR - FORN A QUESTION:
92 TOPIC:
193008 KNOWLEDGE:
Kl.23 QID:
P1591 A reactor had been operating at a constant power level for the last two weeks when a loss of all ac power occurred, thereby causing a scram and a loss of forced reactor coolant flow.
Natural circulation reactor coolant flow developed and stabilized 30 minutes'after the scram.
.Which one of the following combinations of initial reactor power and post-scram steam generator pressure will result in the highest stable natural circulation flow rate 30 minutes after the scram?
INITIAL POST-SCRAM REACTOR STEAM GENERATOR 4
POWER PRESSURE A.
100%
1100 psia B.
100%
1000 psia C.
25%
1100 psia D.
25%
1000' psia ANSWER: B.
l I
I L l 1:
1
USNRC GENERIC FUNDAMENTAI9 EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
93 TOPIC:
193008 KNOWLEDGE:
K1.25 QID:
P793 A reactor enolant system natural circulation coolcown is in progress via the steam generator (S/G) atmospheric steam relief valves (operated in manual control).
If high point voiding interrupts natural circulation, which one of the following will occur?
(Assume feed flow rate, relief valve position, and decay heat level are constant.)
A.
S"3 level decreases and core exit thermocouple (CETC)
-indication increases.
B.
S/G level decreases and CETC indication decreases.
C.
S/G level increases and CETC indication increases.
D.
S/G level increases and CETC indication decreases.
ANSWER:
C. -
l USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOSER 1997 PWR - FORM A I
QUESTION:
94 I
TOPIC:
193009 KNOWLEDGE:
Kl.02 QID:
P1195 A reactor is operating at 80% power at the beginning of a fuel cycle.
All control rods are fully withdrawn and in manual control.
Moderator temperature coefficient is negative.
Which one of the following will decrease the axial peaking (or hot channel) factor?
(Assume no subsequent operator action is taken and that turbine load and xenon distribution do not change unless stated.)
A.
One bank of control rods is inserted 10%.
B.
One control rod fully inserts into the core.
C.
Turbine load / reactor power is reduced by 20%.
D.
Reactor coolant system boron concentration is reduced by 50 ppm.
ANSWER:
C.
QUESTION:
95 TOPIC:
193010 KNOWLEDGE:
Kl.01 QID:
P1896 (Rev)
Brittle fracture of the reactor vessel (RV) is least likely to occur during a of the RV when RV temperature is the reference temperature for nil-ductility transition (RTag).
A.
cooldown; above B.
heatup; above C.
cooldown; below D.
heatup; below ANSWER:
E. I
1
-L8NRC CENERIC. FUNDAMENTALS EXAMINATION OCTO_7ER 1997 PWR - FORN A l
QUESTION:
- 96 TOPIC.
193009 KNOWLEDGE:- K1.07 QID : ~
P1594 (Rev)-
Refer..to the drawing of a fuel rod and coolant flow channel at the beginning of. core life (see figure below).
Given the following initial core parameters:
Reactor power 60%
=
560*F Te..t...
=
2500*F T,
3 e...,u...
=
Which one of the following will be the fuel centerline temperature at the end of core life if the total fuel-to-coolant thermal conductivity doubles?
(Assume reactor power is constant.)
A.
1080*F B.
1250*F C.
1530*F D.
1810*F ANSWER:
C.
CLAD FUEL PELLET
%J r%
%J COOLANT COOLANT PLOW j
FLOW FUEL ROD AND COOLANT FLOW CHANNEL. -. -
-('.
'[-.
USNRC GENERIC - FUNDMGENTALS : EXAMINATION '
OCTO"ER-1997 PWR - FORM A-PROOF:
4
- AT/2 =-(2500'~--'560)/2 Tec = T, + A T = 5 6 0 + 9 7 0.-
= 1940/2.
Tie
~1530*F.
=
.= 970*F:
3-9 l
I i
6 1
4 i
L 1
1 T
j e e
4 6
a 69 -
n b
3..
.-. -. ++-.i.
a.~.-----.-.:...
v,.
...~w w..
.,,. ire.r.,%,
,e-r..
.~r,-.
.,,--y,-
--.v-,,
,----.m_.
y-.
,-y,
,.., - -my
a
.USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:
97 TOPIC:
193010 KNOWLEDGE:
K1.01 OID:
P1296 Which one of the following increases the prc hability of brittle fracture uf a pressure vessel wall?
A.
A high temperature rather than a low temperature B.
A tensile stress rather than a compressive stress C.
Performing a 100*F/ hour heatup rather than a 100*F/ hour cooldown D.
Using materials fabricated from stainless steel rather than carbon steel ANSWER:
B.
QUESTION:
98 TOPIC:
'93010 KNOWLEDGE:
Kl.05 QID:
P2098 (Rev)
Two identical reactors have been in operation for the last 10 years. Reactor A has experienced 40 heatup/cooldown cycles and has an average power capacity of 50%.
Reactor B has experienced 30 heatup/cooldown cycles and has an avercge power capacity of 60%.
Which reactor will have the highest reactor vessel nil-ductility transition temperature?
A.
Reactor A due to the greater number of heatup/cooldown cycles B.
Reactor A due to the lower average power capacity C.
Reactor B due to the fewer number of heatup/cooldown cycles D.
Reactor B due to the higher average power capacity ANSWER:
D. l l
USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOZER-1997 FWR --FORM A
- s QUESTION:_
99
OPIC:
193010
- 7 NOWLEDGE:
K1.06 QID:
.P99 A plant is shut down with the reactor coolant system at 1200 psia and 350*F.
Which one of the following would be most likely to cause pressurized thermal shock of the reactor vessel?
A.
-A rapid depressurization followed by a rapid heatup B.
A rapid depressurization followed by a rapid cooldown C.
A rapid cooldown followed by a rapid pressurization D.
A rapid heatup followed by a rapid pressurization ANSWER:
C.
QUESTION:
100 TOPIC:
193010 KNOWLEDGE:
K1.07 QID:
P1199 e
During cooldown, the thermal stress on the reactor vessel is:
A.
tensile across the entire wall.
B.
compressive across the entire wall.
C.
tensile at the inner wall, compressive at the outer wall.
_D.
compressive at the inner wall, tenLile at the outer wall.
ANSWER:
C.
4.
=
000 FINAL ANSWER KEY 000 OCTOBER 1997 NRC GENERIC FUNDAMENTALS EXAMINATION BOILING WATER REACTOR - ANSWER KEY FORM ANS FORM ANS FORM ANS FORM ANS A
B A
B A
B A
B 1
29 D
26 54 D
51 79 C
76 4
D 2
30 D
27 55 A
52 80 B
77 5
D 3
31 C
28 56 B
53 81 C
78 6
B 4
32 C
29 57 D
54 82 D
79 7
A 5
33 B
30 58 D
55 83 B
80 8
C 6
34 C
31 59 B
56 84 C
81 9
A 7
35 A
32 60 B
57 85 C
82 10 C
8 36 D
33 61 A
58 86 D
83 11 A
9 37 D
34 62 B
59 87 B
84 12 A
10 38 B
35 63 D
60 88 A
85 13 C/D 11 39 A
36 64 B
61 89 C
86 14 B
12 40 B
37 65 C
62 90 A
87 15 B
13 41 D
38 66 A
63 91 C
88 16 B
14 42 D
39 67 A
64 92 D
89 17 A
15 43 A
40 68 B
65 93 D
90 18 D
16 44 B
41 69 C
66 94 B
91 19 A
17 45 C
42 70 C
67 95 D
92 20 B
18 46 C
43 71 C
68 96 D
93 21 A
19 47 A
44 72 A
69 97 D
94 22 B
20 48 C
45 73 B
70 98 D
95 23 D
21 49 A
46 74 D
71 99 C
96 24 C
22 50 C
47 75 C
72 100 B
97 25 D
23 51 C
48 76 B
73 1
D 98 26 D
24 52 A
49 77 A
74 2
A 99 27 C
25 53 C
50 78 A
75 3
A 100 28 C
l
_