ML19325E679
| ML19325E679 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/26/1989 |
| From: | Gallo R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | William Gott Public Service Enterprise Group |
| References | |
| NUDOCS 8911080249 | |
| Download: ML19325E679 (79) | |
Text
.
d UNITED STATES j
// "
g NUCLEAR MEQULATORY COMMISSION 5
in e REOloN 1 S
E 475 ALLENDALE ROAD KING oF PMUSSIA, PENNSYLVANIA 19406 00T 2 6 BB9 Docket No. S r..' 5 4 Public Service Electric & Gas Company ATTN: Mr. W. Gott Train.tng Manager P. O. Box 236 Hancocks Bridge, New Jersey 08038
Dear Mr. Gott:
On October 4,
1989, the NRC administered the Generic Fundamentals
[
Examination Section (GFES) of the written operator licensing examination to employees of your facility.
Enclosed with.this letter are copies of both forms of the examination including answer keys, the grading results for your facility and copies of the individual answer sheets for each of the examinees from your facility who took the examination.
Please forward the results and answer sheet to the examinees. A "P" in the column labeled Final Grade indicates a passing grade for this examination; passing grade for the GFES is 80%.
In accordance with 10 CFR 2.790 of the Commission's Regulations, a copy of this letter and enclosures (1) and ( 2 ) will be placed in the NRC's Public Docto: nt Room (PDR).
The results for individual examinees are exempt from disclosure, therefore, enclosures (3) and (4) will not be be placed in the PDR.
Should you have any questions concerning this examination, please contact Mr. Paul Doyle at (301) 492-1047.
1 Sincerely, Robert M. Gallo, Chief Operations Branch Division of Reactor Safety
Enclosures:
1.
Examination Form "A" with answers 2.
Examination Form "B" with answers 3.
Examination Results Summary for facility 4.
Copies of Candidates individual answer sheets L
l 0FFICIAL RECORD COPY 1
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b 0911080249 891026
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cc w/o enclosures S. Labruna, Vice President - Nuclear J. J. Hagen, General Manager, Hope Creek Operations S. B. Ungerer, Manager, Joint Generation Projects Department, i'?
Atlantic: Electric Company.
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'L. A.IPreston,' General Manager - Licensing and Regulation R. Fryling, Jr.,' Esquire i-Licensing Project Manager, NRR J. Lipot, State of New Jersey Lower.Alloways Creek Township
[.
Public Document Room (PDR) (enclosures 1 and 2 only)
NRC Resident Inspector State of New Jersey-F bec w/o enclosures:
Region I Docket Room (withconcurrences)
Management' Assistant, DRMA P. Doyle, OLB-01 Facility File l
i 0FFICIAL RECO COPY RI:DRS RI:DRS Curl y Cont G lo i
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BWR-GFE (FORM A)
I 1.
B 26.
B 51.
B 76.
A 2.
C 27.
C 52.
A 77.
C 3.
A 28.
D 53.
D 78.
A 4.
D 29.
B 54.
D 79.
C J
5.
A-30.
B 55.
C 80.
B 6.
B 31.
A 56.
D 81.
C 32.
A 57.
D 82.
A 8.
A 33.
D 58.
A 83.
C 9.
D 34.
C 59.
A 84.
A 10.
A 35.
D
- 60. -
D 85.
B 11.
D 36.
A 61.
B 86.
D 12.
D 37.
A 62.
B 87.
B 13.
D 38.
B 63.
C 88.
D 14.
C 39.
B 64.
B 89.
C 15.
D 40.
B 65.
A 90.
D 16.
B 41.
B 66.
B 91.
A 17.
C 42.
C 67.
B 92.
B 18.
C 43.
A 68.
C 93.
C 19.
B 44.
A 69.
A 94.
D 20.
B 45.
C 70.
A 95.
A
- 21. -
A 46.
D 71.
D
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C 22.
D 47.
D 72.
C 97.
D 23.
C 48.
C 73.
A 98.
B 24.
C 49.
C 74.
C 99.
B 25.
D 50.
C 75.
A 100.
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-4 UNITED STATES NUCLEAR REGUIATORY COMMISSION
( - 1 o-SOILING VA*tER REACTOR CENERIC WNDAMEFTALS EXAM SECTION
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J PIM re Print:
Name:
1 7
Facility:
ID Number:
i l
L INSTRUCTIONS TO CANDIDATE l
t so the ansvar sheet provided.
Each question has equal point value.
The l
passing grades require at least 80% on this part of the written licensing examination. All examination papers will be picked up 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the
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examination starts.
t SECTION Questions 4 of Total Score COMPONENTS 1
44
!j REACTOR THEORY 45 - 72
[, -
THERMODYNAMICS 73 100 l
TOTALS 100 p
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All-work dene on this examination is my ovn.
I have neither given f
nor received aid.
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Candidate's Signeture c,
-v FORM A
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NRC RU1E.S AND CUIDELINES FOR THE CENDLIC IVNDMLENTALS EXAMINATION During the administration of this examination the following rules apply:
l
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r (1) Print your name in the blank provided on the cover sheet of the E
examination.
1 I
(2) Till in the name of the facility you are associated with.
1 (3). Till in the ID. Number you were given at registration.
(4) Three handouts are provided for your use during the examination, an l
Equations and Conversions sheet, instr.ictions for filling out the answer l
l sheet, ano Steam Table booklets.
l (5) Use only the answer sheet provided. Credic will only be given for
[
L answers marked on this sheet.
Follow the instructions for filling out i
L the answer sheet.
(6) Scrap paper will be provided for calculations.
L t
(7) Any questions about an item on the examination should be directed to the t
examiner only.
i (8) Cheating on the examination will result in the automat!c forfeiture of I
this examination.
Cheatin6 could also result in severe penalties.
l (9) Restroom trips are limited. Only ONE examinee may leave the room at a time.
In order to avoid the appearance or possibility of cheating, avoid all contact with anyone outside of the examination room.
(10) After you have completed the examination, please sign the statement on the cover sheet indicating that the work is your o.'n and you have not
[
received or been given any assistance in completing the examination.
(11) Please turn in your examination materials answer sheet on top followed by the exam booklet, then examination aids steam table booklets, handouts i
and scrap paper used during thr examination.
(12) After turning in your examination materials, leave the examination area, as defined by the examiner.
If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeited.
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. EQUATION
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8 Cycle Efficiency Net Verk (out) 0 4
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Energy,in) s a
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SUR - 26.06/r M
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1 Curie 3.7 x 10 dps 1 kg 2.21 lbm j
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SOILING WATDt REACTOR CENDt!C FUNDANDITALS EXAMINATION PORN A QUESTION:-
1.
i
.e Which ORE of the following correctly describes the operation of a safety valve l
installed on a high pressure steam system?
j A.
A safety valve is initially lifted off its seat by system pressure, then is forced fully open by an air operated piston.
[
B.
As system pressure increases to the safety set point, the pressure overcomes spring force on the valve operator, causing the valve to open.
j C.
A safety valve will remain open until system pressure has been reduced to l
the pilot valve actuation setpoint.
- ' hen the open safety valve has returned system pressure to the lif ting i
D.
set point, a combination of air and steam pressure above the valve disk I
closes the valve, i
QUESTION:
2.
l i
Which of the following correctly describes the relief mode of operation for a j
i i
A.
The SRV must be manually opened and manually closed using the control i
- switch, B.
The SRV will automatically open, but must be reset by the operator before it will close.
l C.
The SRV will automatically open and close to relieve excess system pressure.
[
D.
The SRV must be manually opened but will automatically close to prevent l
system depressurization.
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L FORM A Page 1 of 35 L
1
SOILING WATER RF. ACTOR CENERIC IVNDAMENTALS EXAMINATION I
FORM A
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QUESTION:
3.
What precaation is applicable, when transferring a controller for a flow control valve from automatic to manual control?
i A.
Verify that both the automatic and manual controller outputs are the same prior to transfer.
l B.
De not attempt to adjust the control signals, since the manual control system tracks the automatic signal ar.d adjusting the signals could negate the automatic tracking, i
C.
Verify that the manual controller output is slightly less than the i
automatic controller's to prevent flow overshoot on the transfer.
I D.
Verify that the nanual controller output is slightly higher than the i
automatic controller's to ensute that no loss of flow occurs on the
- transfer, i
QUESTION: 4 What may be damaged if an operator attempts to manu,111y disengage the motor on a motor. operated valve while the motor is operating?
A.
Limit switches B.
Valve seat C.
Torque switches D.
Clutch QUESTION:
5.
Emergency core cooling systems (ECCS's) typically have testable check valves in the discharge lines from the pump to the vessel.
How does the testable check valve operate?
A The valve is opened by flow and ressure from the discharge of the 2CCS pump.
B.
Instrument air is applied to the valve operator when the ECCS system is shut down to close the valve and ensure no leak across the seat.
C.
The check valve cannot be opened unless the associated ECCS pump is running.
D.
An air solenoid admits air to the valve on system initiation to ensure that the valve opens.
PORM A Page 2 of 35
P v
BOILINC VATER h%CTOR CENERIC }VNDAMENTALS EXAMINATION I
PDRM A QUESTION:
6.
Which statement SEST describes the function and use of valve bachseats?
A.
Valve backseats are provided to remove pressure from the packing and stuf fing box and are the normal method used to isolate the stuffing box for valve repacking.
B.
Valve backseats are provided to remove pressure from the packing and stuffing box and are only used when needed to prevent packing leakage.
C.
Valve backseats are provided as a back up in case the primary seat leaks and are normally used during plant operations, h
D.
Velve backseats ato ptovided es a back up in case the priinary seat leaks and are only used when needed to prevent valves from leaking excessively.
QUESTION:
7.
Civen the equation for mass flow rate:
$=pxAxv where E - mass flev rate (Ibm /sec) p - density of flowing fluid (lbm/ft3)
A - cross section of channel of fluid (f t2) v - average velocity of fleving fluid (ft/sec)
What is the effect on indicated mass flow rate if the liquid being measured has air in solution?
A.
Indicated flow would be greater than actual flow.
B.
Ir.dicated flow would be less than actual flow.
C.
Indicated flow is not affected by air in solution.
D.
The effect on indicated flow is unpredictable.
QUESTION:
8.
A leak develops in the high pressure side of a flow detector. What effect does that leak have on the flow indication of the detector?
A.
The measured delta P will decrease, causing indicated flow to decrease.
B.
The measured delta P will decrease, causing indicated flow to increase.
C.
The measured delta P will increase, causing indicated flow to decrease.
D.
The measured delta P will increase, causing indicated flow to increase.
FORM A Page 3 of 35
(
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BOILING WATER REACTOR CENrJtIC PUNDAMENTALS EXAMINATION c
l-PORN A QUESTION:
9.
i Vhat happens to a fluid as it passes through a venturi?
l A.
Pressure remains constant, but the velocity increases as the diameter of the venturi decreases.
B.
Pressure increases, but the velocity decreases as the diameter of the venturi decreases.
C.
Pressure decreases, but the velocity remains constant as the diameter of the venturi increases.
D.
Pressure increases, but the velocity decreases as the diameter of the venturi increases.
QUESTION:
10.
It is necessary to density compensate the main steam line flow indication because the measured change in pressure across the flow elements is.
A.
directly proportional to the volumetric flow rate.
B.
inversely proportional to the volumettic flow rate.
C.
directly proportional to the mass flow rate.
t D.
inversely proportional to the mass flow rate.
QUESTION:
11.
What is the reason for the reference leg being connected to the reactor pressure vessel (RPV) instead of being filled by a water source independent of the RPV7 A.
To provide a vent path for the prevention of a reference leg rupture during a rapid RPV depressurization.
B.
To alleviate the need for density compensation by keeping the reference leg at the same temperature as the variable leg.
C.
To make the indicated level proportional to the square root of the differential pressure between the reference and variable legs for all reactor pressures.
D.
To provide compensation for the RPV pressure exerted on the variable leg.
l FORM A Page 4 of 35 l
.+-
ij BOILING WATER REACTOR CENERIC MINDAMENTALS EXAMINATION l
KEN A QUESTION:
12.
If the variable leg temperature of a differentie1 pressure level cell is
[
higher than the calibration conditions, what vill the level instrument i
indicate?
A.
Indicated reactor water level is highet than actual reactor water level.
B.
Actual level if the reference leg temperature is at the calibration conditions C.
Actual level if the reference leg temperature is the same temperature as the variable les D.
Indicated reactor water level is lower than actual reactor water level.
QUESTION:
13.
Vhat will the indication be when a level D/P cell fails (D/P - 0)?
A.
On of full range B.
50% of full range C.
75% of full range D.
100% of full range QUESTION:
14.
Which of the following correctly describen a characceristic of a thermocouple?
A.
Indication will fail high offscale with an open circuit.
B.
They are generally more accurate than resistance temperature detectors (RTDs).
C.
A junct!on between two dissimilar metals will generate a voltage proportional to temperature.
D.
A junction between two dissimilar metals will result in a change in electrical resistance proportional to temperature.
FORM A Page 5 of 35
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BOILING UATER REACit)1t CENEILIC FUNDAMENTAIJ EXANINATION PoltN A
+
s; QUESTION:
15.
L The difference between the setpoint and the measured parameter in an automatic flow controller is called:
i.
A.
gain.
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s j
3.
bias.
I.
C.
feedback.
t D.
error.
QUESTION!
16.
k'hich of the following valves is MOST LIKELY to be used with a throttling positioner?
A.
Stop valve e
B.
Globe valve C.
Cate valve D.
Butterfly valve QUESTION:
17.
The governor on an emergency diesel generator regulates the amount of fuel supplied to the diesel engine to:
A.
increase engine speed as load increases.
B.
increase generator ve'.ttage as load increases.
C.
maintain engine speed nearly constant as load changes.
i D.
maintain generator voltage nearly constant as load changes.
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FORM A Page 6 of 35 i
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B01LINC VATER REACTOR CENERIC TVNDAMENTA13 EXAMINATION IDRM A QUESTION:
18.
Venting a centrifugal pump prior to operating it ensures that:
l A.
pump runout will not occur.
i B.
pump internal corrosion is reduced.
C.
gas binding is reduced.
l D.
starting load is minimized.
+
t QUESTION:
19.
k' hat v uld result from operating a motor driven centrifugal pump for extended perioca of tive with the discharge valve shut?
A.
No damage, since the pump and motor are designed to operate with the discharge valve shut B.
Pump overheating, cavitating, ant. ultimately failure C.
Excessive motor current, damage to motor windings, and ultimately motor failure D.
Pump and motor speeding excessive 1.y and tripping on high motor current QUESTION:
20.
A centrifugal pump is operating at rated speed with an cutput head of 240 peig. The speed of the pump is then decreased until the powe consumption is 1/64 of its original value.
k' hat is the approximate new output head?
A.
3.75 psig l
B.
15 psig C.
30 psig D.
60 psig l
IVRM A Page 7 of 35
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BOII.ING WATER REACTOR CENERIC FUNDAMENTALS EXAMINATZOW FORM A
, QUESTION:
21.
k' hat will incres reactor recircule. tion pump available net positive suction o
i head' (Assume a other parameters remain constant.)
1,.
A.
Loss of feeowater heating while at 80% power j
B.
Increase in reactor coolant temperature from 100'r to 200'r during a reactor startup C.
Decrease in reactor pretsure during a normal reactor shutdown D.
Decrease in reactor water from the normal level to just below the low level alarm level j
QUESTION:
22.
k'hich one of the following items is EI a characteristic of centrifugal pumps operatitig in reries?
A 1he available net positiNe suction head (NPSH) of the second pump in the series is greater than the NPSH in a single pump system.
B.
The capacity for two pumps operating in series is limited by the capacity of the first pump in the series.
C.
The total head for two pumps operating in series is approximately twice j
the head for a single pump supplying the same capacity.
D.
The power required to supply two centrifugal pumps operating in series is less than twice the power required for each of the individual pumps.
QUESTION:
23.
k' hat is caused by operating a motor dri'r.1 centrifugal pump under runout conditions?
A.
Pump failure due to excessive pump cavitation.
B.
No damage, since the pump and motor are designed to operate without failure under pump runout conditions.
C.
Motor failure due to exce ssive current being drawn through the motor I
windings.
D.
pump failure due to overheating, caused by the increased impellor to-casing friction.
MRM A Page 8 of 35
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BOILING UATER REACTOR GENERIC MINDMtDITA1A EXAMINATION i
PORN A l
1'
-QUESTION:
24.
t L
A single. speed centrifugal fire pump takes auction on a storage tank and i
L diccharges through a flexible fire hose.- Vhich of the following correctly describes.the response of the pump discharge flow rate?
l I'
A.
Remain constant as the elevation of the pump discharge piping is raised i
l.
Increase as the elevation of the pump discharge p'aine is raised B.
1 C.
De'erease.as the level in the storage tank on the pump suction is lowered j.
s j
L D.
Remain constant as the level in the storage tank on the pump suction is lowered I
l QUESTION:
25.
l What will occur by operating a positive displacement pump with insufficient l-not positive suction head?
i A.
Slip e
i B.
Decreased pump speed C.
Water hammer D.
Vapor binding I
QUESTION:
26.
i For large electric motors, why must the number of starts over a period of time i
be limited?
A.
Protect the power supply cabica from insulation breakdown due ca high starting current l
B.
Protect the motor. windings from overheating C.
Prevent motor thruse bearing damage due to lack of lubrication D.
Prevent rotor seizura due to thermal expansion of the winding 6 caused by high starting current 8
i i
FORM A Page 9 of 35 l-
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Boll.ING WATER REACTOR CENERIC sVNDnMENTAIE EXANINATION FORM A QUESTION:
27.
Given the following conditions for a variable speed motor drivan centrifugal pump:
i' Flow rate
- 2000 bpm Motor current - 100 amperes i
If the flow rate is increased to 4000 gpm, which one of the following motor i
current values MOST,CLDSELY approximatos the actual value?
A.
200 amperes B.
400, amperes C.
800 amperes x D.
1600 amperes l
p QUESTION:
2 8.-
Vhich of the following best describes the motor current indications that would I
be observed during the start of a large A.C. motor at full load?
A.
Amps slowly increase to the full load value.
B.
Amps immediately increase to the full load value, f
C.
Amps immediately increase to approximetaly three times the full load value and then decrease to the full-lovt value.
D.
Amps immediately increase to approximately six times the full load value and then decrease to the full load value.
QUESTICS:
29.
Which.of the following correctly describes the effects on generator excitation with the generator paralleled to the grid?
A,
!ncreasing field current increases excitation and shifts power factor from lagginr toward leading.
B.
Increasing field current increases excitation and shifts power factor from leading.oward lagging.
C.
Decreasing field current ine: eases excitation and shifts powcr factor i
from leeling toward lagging.
l D.
Decreasing field current increases excitation and shifts power factor from leading toward lagging.
FORM A Page 10 of 35 l
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BOILING WATER REACTOR GENFAIC FUNDAMENTA13 EXAMINATION h
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F3RN A i
4 QUESTION: -30.
As steam (she'.1) and liquid (tube) heat exchangers are put into service. the:
A.
steam side is valved in before the water side to'ainimize scale buildup t
on the heat exchanger tubes.
B.
water side is valved in before the steam side to prevent thermal shock from occurring.
C.
water sida 'is valved in before the steam side to ensure adequate venting.
D.
steam side is valved it. before the water side to ensure that the cooldown rate does not exceed 100 'F/hr.
QUESTION:
31.
Decreasing the temperature of a cooled system using a shell and tube heat exchateger is NORMALLY ac::omplished by:
A, increasing the cooling system flow.
B.
increasing the cooled system flow.
C.
decreasing the tooling system flow.
D.
decreasing the cosled system flow.
QUESTION:
32.
k*hich of the following changes will PECREASM subcooling of the condensate vater?
A.
1:olate one bay of the condenser circulating water system.
b.
Decrease circulating water temperature.
C.
' Increase circulating water flow.
I f-D.
Decrease the rrain turbine generator Megawatt load.
FMM A Page 11 of 35
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BOILil0C VATER ILEACTDR CDIERIC MINDAMENTA13 EXAMINATION c.
FoltM A j
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QUESTION:
33.
During normal reactor operation, a main condenser develops an air leak which J
decreases vacuum at a rate of 1 in Hg/ min. Which of the following plant parameters would be the FIRST to show an INCREASE because of this condition?
A.
Extrcction steam flow B.
Generator megawatt output C.
D ulating water outlet temperature D.
Condensate temp 2rature QUESTION:
34 Whct is the saturation temperature for a boiling water reactor (BVR) operating at 920 psig.?
[Use steam tables.)
A.
532.6 'F B,
533.9 *F C.
536.5 *F D.
538.4 'F
, QUESTION:
35.
Why should fouling of heat exchanger tubes in closed cooling vater systems be MINIMIZED?
A.
To prevent excessive heat transfer rates.
B.
To provent the cooling water outlet temperature from exceeding design limits.
i C,
To maximize the prssure drop acrosa the heat exchanger.
D.
To ma.:imize the heat transfer rate.
l
'fDRM A Page 12 of 35
80118.NC VATER REACTOR CCNERIC IVNDAMENTAiJ f*KANINATION j'
}DRM A
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QUESTION:
36.
Vhy is proper venting ci a shell and tube hoat exchenger inportant?
A.
An air bubble reduces the heat transfer coefficient of the heat exchanger.
.t
/
B.
An air bubble causes pressur.' transients withi.) the tubes as heat load changes.
C.
An air bubble will cause thermal shock as it moves through the heat exchanger.
D.
At air bubble will cause corrosion in the heat exchanger.
QUESTION:
37.
What is the purpose of a mixed bed demineralizer?
A.
To remove both positively and negatively charged ions.
B.
To reduce the conductivity without affecting the pH of the water.
C.
To increase pH by reducing the number of positively charged ions in the water.
D.
To increase the conductivity of the water to greater than 1.0 micronhos.
i QUESTION:
38.
1; a demineralizer, what adverse effect occurs due to channeling?
A.
Reduction of delta P across the demineralizer because the resin is essentir.11y bypassed B.
Reductian in demineralization efficiency because the re in is essentially bypassed C.
Loss of resin due to agitation as a result of increased velocity through the demineralizer D.
Resin damage due to the increased velocity of fluid through the demineralizer FORM A Prge 13 of 35 l
i i
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SOILING WATM REACTOR CMMIC FUNDAMENTA13 UANINATION-b FORK A QUESTION:
39.
s The fitst indication of resin depletion in the effluent of a demineralizer is:
A.
a decrease in suspended solids.
B.
an increc;a in the conductivity.
C.
a decrease in chlorides.
D.
an increase in resin fines.
[
QUESTION:
40.
If the breaker control power is lost to a supp1; breaker for in operating pump motor, the breaker:
A.
V'11 trip on undervoltage.
S.
will remair. clos.'nd until tripped locally by an operator.
j C.
will remain closed unless a fault trip occurred.
D.
will remain closed until tripped ren tely ny an operator, QUESTION:
41.
/l f
][
What is the definition of a thermal overload device?
A.
A balanced circuit that compares actual current to a fixed overcurrent signal which, when exceeded, trips a relay.
B.
An in line thermal coil that, when subjected to a high current, overheats and actuates a circuit interrupting device.
C.
A temperature monitor that senses the temperature of the operatine.
equipment and trips the circuit breaker if the temperature exceeds preset
- limits, D.
An induction coil that generates a secondary current proportional to the i
primary current, closing the trip circuit contacts.
j
-l i
L l i.
FORM A Page 14 of 35 1^t 1
I -'
A0!!.IllG UATEL REACTOR CENDt!C ft9EDANDTTA12 EXANINATION l
f.
PORM A C'
QUESTION:
42.
Never open or close a high voltage (greater than 750 volts) air break disconnect unless:
[
A.
the current flowing through it is approximately zero.
l t
B.
the current flowing through it is less than its design current carrying capability.
i
\\
C.
the circuit it is in is already open.
D.
a parallel path exists for current flow.
i t
QUESTION:
43.
l If a generator output breaker is closed with f.enerator frequency lower than grid frequency. what will result?
(Assume that no generator relay protection i
is actuated.)
j A '.
The generator vill motorize.
B.
The voltage of the generator will decrease to compensate for the lower
' h,.
frequency.
i
- l' C.
The generator will accept too much load.
D.
The entire connected system will operate at the frequency of the lowest frequency (the oncoming) generator.
j i
i QUESTION:
44.
I For a circuit breaker placed in the test position, which of the following statements is correct?
5 A.
Control power is available te the breaker and functions normally to open i
and close the breaker.
b.
Tne test positien can only bc used to test a circuit breaker on a deed bus.
C.
The main power contacts remain connected to the load, but the breaker tr ps free when tested.
D.
The f:est position disables the overload devices, allowing them to be set during normal cieration.
FORM A Page 15 of 35 t
is
pg+
t-SOILINC VATER REACTOR CDIERIC PVNDAMENTALS EXAMINATION 3
FORM A QUESTION:
45.
I The term neutron generation time is MOST ACCURATELY defined as the average time between:
I i-A.
neutron absorption and subsequent fission.
s B.
the production of a delayed neutron and subsequent neutron absorption.
C.
fission and subsequent production of a neutron.
D.
neutron thermalization and subsequent neutron absorption.
l QUESTION:
46.
I K,gf is HQI dependent on:
A.
core dimensions.
5.
core burnout.
C.
mouerator to. fuel ratio.
D.
installed neutron sources.
t 6
QUESTION:
47.
j The fractional change in neutron population from one generation to the next is I
- called, i
A.
be:4.
i 0*
eff*
C.
Iambda.
D.
reactivity.
l r
L h-I 9
l-FORM A Pabe 16 of 35
w d'
BOILING WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION
}YRM A QUESTION:
48.
What ia the definition for DELAYED NEUTRON l'RACTlQti?
A.
Traction of the total number of delayed neutrons produced from fission, born from delayed neutron precursors B.
Traction of the total number of fast neutrons produced from fission, born from delayed neutron precursors u
C.
Traction of the total number of neutrons produced from fission, born from delayed neutron precursors I,.
Traction of the total number of thermal neutrons produced from fission, born from delayed neutron precursors.
QUESTION:
49.
Af t er initial criticality, the reactor period is stabilized.
The source range channels are rc,sositioned so that the count tate is 100 eps.
Sufficient positive reactivity is added to establish a 120 second period.
How much time will it take for the count rate to increase to 10,000 eps with no additional operat: ' action?
A 1.2 minutes B.
4 minutes C.
9.21 minutes D.
15.82 minutes QUESTION:
50.
~
During a reactor startup, the reactor is critical at 3000 counts per second.
A control rod is notched out, resulting in a doubling time of 85 seconds. How much time is required for the reactor to reach 888,000 eps?
A.
483 seconds l
B.
612 seconds C.
697 seconds D.
965 seconds IVRM A Page 17 of 35
- is '.
BOILINC WATER REAC1TML CENERIC FUNDAMENTA1E EXANINATION
]
PORN A j
^ QUESTION:
51.
The change in reactivity produced by a unit change in reactor coolant temperature, defines which reactivity coefficient?
A.
Void' B.
Moderator i
C.
Power D,
Doppler i
i QUESTION:
52.
Assume a reactor had been shut down for a shift, and shutdown coolit.g is in
]
service. Which of the following coefficients of reactivity will act f.1ESI to j
change core reactivity upon a loss of shutdown cooling?
A.
Moderator temperaturs coefficient B.
Doppler coefficient i
C.
Void coefficient D.
Pressure coefficient QUESTION:
53.
In regard to core parameters tF.,
affect control. rod worth, which QHE of the following statements is correct.
A.
- ontrol rod worth decreases in areas of increased flux due to rod shadowing.
B.
control rod worth increases with an increase in voids.
C.
control rod worth increases with an increase in fast neutron flux.
D.
control rod worth decreases when epproaching end of core life (EOL).
r FORN A Page 18 of 35
(
BOILING VATER REACTOR CENDLIC FUNDAMENTA!E EXAMINATION a
FORM A QUESTION:
54 The reverse power effect or reverse reactivity effect occasionally observed when a shallow control rod is withdrawn one or two notches is due to relatively:
i A.
large local power increase being offset by a moderator temperature.
related power decrease, j
B.
small local power decrease due to the shadowing effect of nearby control l
rods.
j C.
small local power decrease due to increased local Doppler effects.
l large local power increase being offset by a void related power decrease.
D.
4 QUESTION:
55.
Vhat are the substances in the correct order, from LARCEST TO SKALLEST, of microscopic cross section (Thermal Neutrons) for capture?
A.
U 235. H20, Xe 135 B.
U 235, Xe 135 H2O C.
Xe 135, U 235. H2O D.
Xe 13$, H20, U 235 E
QUESTION:
56.
A reactor has been shut down fot-2 weeks after extended power operation. What control rod movement is required to maintain 10 percent stable power immediately after startup?
~
A.
Small amounts of rod insertion to compensate for LpRM chamber depletion.
B.
Small amounts of rod withdrawal to compensate for Samarium buildup.
C.
Small amounts of rod insertion to compensate for installed poison burnout.
D.
Small amounts of rod withdrawal to compensate for Xenon buildup.
FORM A page 19 of 35
h B0lLING WATER REACTOR CDIERIC FUNDAMENTALS EXAMINATION 6
FORM A QUESTION:
57.
{.
Following a reactor trip from a long term, steady. state,100 percent power run, the reactor in to be taken critical.
The calculated estimated critical conditions ' (position) are based on a KENON-FREE core. What is the shortest time after the initial trip that this condition would exist?
i' A.
8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> B.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C.
40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> D.
70 to 80 houre
?
QUESTION:
58.
If. equilibrium reactor power level is increased from 50 percent to 100 percent, equiliorium xenon concentration will increase to a level that is:
I A.
less than twice the 50 percent power concentration.
B.
equal to twice the 50 percent power concentration.
C.
more than twice the 50 percent power concentration.
I D,
unpredictable unless the exact duration of operation at the two power levels is known.
i QUESTION:
59.
A reactor has been operating at 50 percent power for one week when power is
'l quickly ramped (over four hours) to 100 percent power. How would the Xenon concentration in the core respond?
A.
Decrease, then build up to a new equilibrium concentration in 40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> B.
Increase to a new equilibrium concentration in 40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> C.
Decrease, then quickly build up to a new equilibrium concentration in eight to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> D.
Remain the same because Xenon concentration is independent of flux level e
1 FORM A Page 20 of 35
w BOILINC WATFJL REACTOR CENERIC MINDAMDfTAIE EXAMINATION a
FORM A l
QUESTION:
60.
i What is t e difference in peak xenon concentration following a reactor scram h
after 1 week at 100 percent power as comparcd to a serem af ter 1 week at 50 percent power?
A.
The time to reach the peak is shorter after 100 percent power than after 50 percent power, due to the higher iodine decay rate.
B.
The peak from 50 percent is of a smaller magnitude due to the lower Xenon burnout rate.
C.
The peaks are equal because the decay rate of iodine remains constant.
D.
The peak from 100 percent power is of a larger magnitude, due to the larger initial iodine concentration.
t QUESTION:
61.
When comparing control rod worths during a reactor startup from 100 percent peak xenon and a reactor startup from xenon free conditions:
A.
center control rod worth will be higher during the peah xenon startup than during the xenon free startup.
B.
peripheral control rod worth will be higher during the peak xenon startup than during the xenon free startep.
C.
both control rod worths will be the same regaroless of core xenon conditions.
D.
it is irp.reible to determine how xenon will affect the worth of center and peripheral control rods.
QUESTION:
62.
A reactor has been operating at 100 percent power for about two weeks when power is reduced to 50 percent. What is going to happen to the Xenon 135 concentration in the core?
A.
There will be no change because Iodine concentration is constant.
B.
Initially Xenon will increase, then decrease to a new lower equilibrium value.
C.
Initially Xenon will decrease, then increase to a new higher equilibrium value.
D.
Xenon will decrease to a new equilibrium value.
FORM A Page 21 of 35
- -~
[
SOILING WATER REACTt* CDIERIC FUNDAMENTALS EXAMINATION FORM A QUESTION:
63.
If a reactor that has operated at 100 percent power for ten days is shut down rapidly, xenon concentration will L
[.
A.
slowly decay away to almost zero in three days.
l B.
increase to a new equilibrium in three days.
C.
peak in about a half day, then decay to almost zero in three days.
D.
ramp down with reactor power.
QUESTION:
64,
(
Vhat is the definition of the tern BURNAdLE p0ISON?
A.
Isotopes manufactured into the fuel with large scatter macroscopic cross i
sections.
B.
Thermal neutron absorbing material added to the fuel, during the manufacturing process.
C.
Neutron absorber materials produced in the fuel by fast neutron absorption.
l l
D.
Fast neutron absorbing material loaded into the upper third of the core to aid in slowing down neutrons.
QUESTION:
65.
During a reactor startup, as K approaches unity, which of the following statementsiscorrectforEOUA[.fbOSITIVEREACTIVITYADDITJ2ES?,
i i
A.
The changes in neutron population are larger.
B.
As the neutron population increases, the number of neutrons lost per generation decreases.
l C.
The number of fast neutrons gained per generation increases more slowly.
l D.
A step increase in X increases the neutron population and thereforo l
decreasesthenumber*bfneutronslostpergeneration.
l l
FORM A Page 22 of 35
f,_-
T BOILING UATER REACTOR CENERIC MiltDAMENTA1A EXAMINATION FORM A QUESTION:
66.
During reactor startup, critical rod position is HQI affected by:
s s
A.
control rod worth.
B source range initial count rate.
6
?
C.
fuel temperature.
D.
core age, QUESTION:
67.
Duringareactorstartup,asK,buetotheincreasedeffectof:
approaches 1.0, it takes longer to reach an f
equilibrium neutron count rate A.
prompt neutrons.
L B.
delayed neutrons.
C.
fast neutrons.
i D.
slow neutrons.
i QUESTION:
68.
Assume a reactor is critical at a power level below the point of adding heat.
For ar equal positive reactivity insertion, the reactor period would be:
A.
shorter if the core were xenon free.
B.
longer at EOL than at BOL.
C.
shorter at EOL than at BOL.
D.
longer at higher moderator temperature.
l P
l i
s h
FORM A Page 23 of 35 l'
BOII.ING WATER REACTOR CENERIC WNDAMDf7A13 EXAMINATION FORM A QUESTION:
69.
For which one of the following events will the Doppler coefficient act FIRST to counteract the reactivity addition to the core?
l A.
A control rod drop during reactor power operation B.
The loss of one feedwater heater (extraction steam isolated) during reactor power operation C.
Tripping of the main turbine at 45 percent reactor power D.
A safety relief valve opening during reactor power operation QUESTION:
70.
A reactor is operating at 100 percent power and flow.
Reactor power is reduced by driving control rods in.
(Recirculating pump speed remains censtant.) What is the effect on core flow?
A.
Core flow will increase, due to the decrease in two. phase flow resistance.
E.
Core flow will remain constant, since reactor power does not affect core flow.
C.
Core flow will decrease, due to an increase in two phase flow resistance.
D.
Core flow will increase, due to the increase in recirculation ratio.
QUESTION:
71.
What is the effect of isolating extraction steam to a high pressure feedwater heater while at 90 percent of rated power?
A.
The core inlet subcooling remains the same while the turbine generator MVe output decreasee.
B.
The core inlet subcooling and the reactor power (MVt) decrease.
C.
The reactor power (MVt) and the turbine generator MWe output remain the same.
D.
The core inlet subcooling increases and the turbine generator MVe output increases.
FORM A Page 24 of 35
7,. _
SOILING UATER REACTOR CENERIC FUNDMEDfTAIA EXAMINATION FORM A QUESTION 72.
l Shortly after a reactor trip, reactor power indicates 0.5% when a stable j
negativo startup rate (SUR) is attained.
Reactor power will be reduced tv 0.054 in approximately
- seconds, i
A.
360
[
B.
270 C.
180 L
D.
90 i
L t
t i
L i
e i
i t
l i
r l
I l
I t
i l
MRM A Page 25 of 35 1.
l
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r,
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BOILING WATER REACTOlt CENETtl*; FUNDAMENTAIE T4stINATION 4
l;7. n Iux A
~
'o QUESTION:
73.
r,
A differential pressure manometer filled with water is installed across an h,CM;
-orifice In a ventilation duct to determine the direction of airflow, as shown ircthe figure below.
What are the conditions in the ventilation duct?
A.
P1 is greater than P2, and airflow is to the right.
B.
P1 is greater than P2, and airflow is to the left.
C.
'P1 is less than P2, and airflow is to the right.
D.
P1 is less than P2, and airflow is to the left.
QUESTION:
74
'Given an operating reactor at 985 psig and a feedwater inlet temperature of 400
'F, what will'be-feedwater subcooling?
lf..
A '.
136.6F
<L B.-
140.6 'F-C.
144.6 'F 4
D.
148.6'*F QUESTION:
75.
The saturation pressure corresponding to 400 'F is:
A.
247.3 psia B.
262.0.psis I
a
'C.
335.3 psia D.
350.0 psla t
(
l,,
FORM A Page 26 of 35
.e a
i n --
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I! '
BOILING WATER REACTOR CENERIC PVNDAMENTALS EKANINATION i
4 FORN A L
I*
' QUESTION: 76.
[
L fi 14 The area of a steam jet air ejector (SJAE) where the LOVEST pressure exists is located at the:
.o-A.
throat of the nozzle.
9
+1 B.
inlet to the nozzle.
C.
outlet of the nozzle.
D.
suction piping from the condenser to the SJAE.
s.
QUESTION:
77.
Condensate depression (subcooling) is increased by increasing:
A.
main turbine load.
B.
the circulating water temperature.
C.
circulating water flow through the condenser.
D.
air leakage into the condenser.
-QUESTION:
78.
The. thermodynamic cycle efficiency of a power plant is increased by:
A.
decreasing the amount of condensate depression (subcooline).
'B.
removing'a high-pressure t'eedwater heater from service.
C.
lowering condes=er vacuum from 29 inches to 25 inches.
D.-
decreasing power from 100% to 25%.
y QUEt 'ON:
7).
If a valve closure suddenly stops fluid flow, the resulting piping system y2 pressure changa is referred to as:
A.
cavitation.
B.
shutoff head.
C, water hammer.
m D.
valve chatter.
FORM A Page 27 of 35
'l I
b i
[,
5.
.L ~ -
,a BOILINC. WATER REACTOR CENERIC INALS EXAN1 NATION -
FORM <A L"
QUESTION:
'80.
0[
The condition that would most likely cause cavitation of an operating pump is:
A.
Iowering the suction temperature.
U B.
throttling the pump suction valve.
i C.
throttling the pump discharge valve.
1 D.
decreasing'the pump speed.
QUESTION:
81.
If two identical centrifugal pumps are operating in FARALLEL, then:
A.
the t'otal brake horsepower for the system is more than twice the horsepower of an individual pump, B.
the total head for the system is the sum of the two individual pump capacities.
C.
the total capacity of the system is the sum of the two individual pump capacities.
+
D.
the total brake horsepower for the system is the sum of the individual pump brake horsepowers.
QUESTION:
82.
Net positive suction head (NPSH) is:
A..
the difference between r" jap suction pressure and the saturation pressure of the fluid being pumped.
B.
the difference between the total suction head and the pressure at the eye of the pump.
C.
toe amount of suction pressure required to prevent cavitation.
l D.
the differ-ns. between the pump suction pressure and the pump discharge l,
pressure.
l I,
1 l-i FORM A Page 28 of 35 l\\
f{'j 4-
' BOILING WATER REACTOR CENERIC WNDAMENTALS E'%MINATION g
g FORM A y
. QUESTION:
83.
i Q,
'A' boiling water reactor (BWR) is operating at a pressure of 1025 psia It has k,
a temperature of 530 'T in the suction of the recirculating pump and an p'
- elevation head of 25 psia. Neglecting line losses, what is the net positive
}.
suction head (NPSil)?
A ','
148' psia B.
154 psia t-C.
165 psia' D.
171 psia QUESTION:
84 An acceptable method to reduce water hammer in emergency core cooling systems is to:
5 A.
maintain the system full of liquid (vented).
B.
ensure minimum flow paths are maintained.
C.
maintain minimum NPSH requirements.
D.
start pumpa sgainst shut off head.
1 QUESTION:
8.5.
The heat-transfer mechanism using direct contact transfer of kinetic energy l
from molecular motion is:
l.
A.
convection.
B.-
conduction.
C.
radiation.
D.
transmission.
l 1
FORM A Page 29 of 35 5
d
p P
e BOILING VATER REACTOR GENERIC FUNDAMENTALS EXAMINATION
- ..e FORM A l
)
QUESTION:
86.
r The correct order of boiling heat transfer mechanisms, from the MOST EFFICIENT to the LEAST EFFICIENT, is:
A.
stable film boiling, transition boiling, nucleate boiling.
B.
nucleate boiling, stable film boiling, transition boilf.ng.
C.
transi'. ion boiling, nucleate boiling, stable film boiling.
b D.
nucleate boiling, transition boiling, stable film boiling.
QUESTION:
87.
The dominant heat transfer mechani-m that occurs whet: film boiling is present
'is:
A.
convectien, B.
radiation.
C.
conduction.
D.
induction.
QUESTION:
88.
The llICllEST heat transfer from the fuel-cladding surface to the coolant channel is provided by:
A.
forced convection with subcooled coolant (no boiling).
~
B.
natural convection with subenoled coolant (no boiling).
C.
natural convection with bulk boiling of coolant.
D.
forced convection with nucleate boiling.
g l
l FORM A Page 30 of 35
k BOILING WATER REACTOR' CENERIC FUNDAMENTALS EXAMINATION-J.
FORM A L
QUESTION:
89.
+
Thu correct oroer of the heat transfer mechanisms existing in the boiling water reactor (Lk'R) core (consider inlet to outlet flow) is:
i.
A.
subcooled nucleate boiling, single phase convection, slug flow, annular flow.
B.
-annular flow, single phase convection, subcooled nucleate boiling, sivg
- flow, t
- C.
single phasa convection, subcooled nucleate boiling, slug flow, annular i
(
flow.
D.
single phase convection, subcooled nucleate boiling, annular flow, slug flow.
i s
. QUESTION:
_90.
3 Boiling improves heat transfer because:
A.
it increases the effective thickness of the fluid film surrcunding the heat transfer surface.
B.
it increases tho' fluid velocity past the heated surface, which offsets the reduction in fluid film thickness at the heated surface.
C.
it increases the heat transfer from the heated surface due to the latent heat of condensation, as the steam bubbles collapse at the heated surface.
D.
it produces agitation, which reduces the thickness of the fluid film and results in the latent heat of vaporization beinB removed, as the bubbles move away from the heated surface.
i l
FORM A Page 31 of 25 i.
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[
SOILING WATFR REACTOR GENERIC FUNDAMENTALS EXAMINATION
[-
FORM A F.
, -i QUESTION:
91.
n Select the statement which best describes transition (partial film) boiling.
1 A.
A small increase'in delta T (at the-heat transfer and coolant interface) causes increased steam blanketing and a reduction in heat flux.
b B.
The temperature of the heat transfer surface is so high that thermal radiative heat transfer becomes significant and heat flux ineceases.
.C.
As the delta T increases, the increasing number of bubbles causes increased agitation and turbulence of the boundary layer consequently increasing heat flux.
D.
As the delta T increases a few vapor bubbles are formed which may collapse when they enter into the bulk of the fluid.
QUESTION:
92.
The onset of transition boiling (OTB) is:
A.
the area on a heat transfer curve where the most energy is added to the coolant.
B.
the period when clad temperature fluctuates as the heat transfer coefficient alternates between a high value and a much lower value.
C.
the most effective means of heat transfer.
D.
the period when clad temperature remains constant as the heat transfer coefficient becomes negative.
QUESTION:
93.
The relationship between BUNDLE POWER and BUNDLE FIDW RESISTANCE characteristics is:
A.
flow resistance decreases as the quality and two-phase flow increase.
B.
prior to boiling, as bundle power increases, bundle flow decreases, s
C.
flow resistance increases as the quality ai.d void fraction increase.
D.
flow orifices minimize the undesirable effects that quality decrease produces on bundle flow.
l l
FORM A
' age 32 of 35
m(
L-BOILING WATER REACT 0k GENERIC FUNDAMENTALS EXAMINATION FORM A l
QUESTION:
94.
r '
Linear Heat Generation Rate (LHCR):
A.
is the ratio of the power produced in a given fuel bundle divided by total core thermal power.
t B.
is-the ratio of the everage power per rod divided by the rod power at 100% power.
C.
is'the sum of the power produced by all fuel rods in a given fuel bundle at a specific planar cross section.
D.
Is the sum of the power per unit area for each unit area of the fuel cladding for.a unit length of a fuel rod.
QUESTION:
95.
(-'
The fraction of the limiting power density (FLPD) is equal to:
A.
IBOR (actual)
LHCR (design)
'B.
ATPF + RPF c.
III APF D.
LHJR limit CPR i
QUESTION:
96.
Which one of the following parameter changes will cause an increase in the I
' critical power of a fuel bundle?
~~
l l
A.
The subcooling of the coolant entering the bundle decreases.
B.
The local peaking factor increases.
C.
The coolant flow through the bundle increases.
D.
The axial power peak shifts from the bottom to the top of the bundle.
l FORM A Page 33 of 35
5 T
BOILING WATER REACTOR CENERIC FUNDAMENTAL 3 EXAMINATION
)y FURN A
' QUESTION: 97 I'
Operating the reactor within limits defined by.the maximum average planar iC-linear heat generation rate (MAPLHGR) prevents:
A.
-exceeding 1 percent plastic strain in the cladding.
- r 3
.B.
-exceeding peak fuel temperatute of 2200
'F.
C.
the onset'of transition boiling in the upper core.
[
D.
exceeding a peak clad temperature of 2200 'F.
QUESTION:
98.
6 C
' The~ fuel bundle power that would cause the onset of transition boiling at some
,i
- point in the fuel bundle is the:
A.
. technical specification limit.
{
B.
critical power.
C.-
maximum fraction of limiting power density, r
D.
maximum power density.
N QUESTION:
99.
t The threshold power for Pellet Clad Interaction (PCI) decreases as! fuel exposure increases because:
l
' A heat transfer capability is reduced by buildup of fission products and.
crud layers.
R B.
chemical embrittlerent of cladding occurs due to fission product ;ases.
C'.
- pellet densification occurs due to fuel burnout.
- D.
zirconium hydriding is reduced with fuel burnup.
ll H
FORM A Page 34 of 35 Y
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' "T V 3
s
(
' d.
- l.. -
't BOILING WATER REACTOR CENERIC FUNDAMENTALS EKAMINATION.
i yong A I.
-QUESTION:. 100.
1 The likelihood of brittle fracture failure of the reactor vessel is reduced' by:
o'*
A.
increasing vessel age.
B.
- reducing vessel pressure.
C.
reducing vessel teuperature.
D, reducing gamma flux exposure, t-p,,
4 4
k g
9 i
FORM A Page 35 of 35 i
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r s,,:.
e
G
[ nebs m e s
e, a
BWR-GFE (FORM B) l
-1.
A 26.
B bl.
C 76.
C 2.
C 27.
B 52.
C 77.
C 3.
A 28.
's 53.
D 78.
C 4.
A 29.
B 54.
B 79.
B 5.
C 30.
C 55.
C 80.
A 6.
A 31.
A 56.
D Bl.
D 7.
C 32.
D 57.
B 82.
D B.
B 33.
A 58.
B 83.
C 9.
C 34.
B 59.
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A 85.
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C 36.
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A 37.
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A 63.
D 88.
D 14.
D 39.
D 64.
A 89.
B 15.
B 40.
D 65.
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D 41.
D 66.
B 91.
C 17.
C 42.
C 67.
B 92.
B l
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D 43.
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B 93.
A 3
19.
A 44.
B 69.-
B 94.
B 20.
B 45.
C 70.
C 95.
B 21.
C 46.
C 71.
A 96.
C l
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D 47.
B 72.
A 97.
A 23.
A 48.
B 73.
C 98.
A 24.
C 49.
A-74.
D 99.
D 25.
D 50.
D 75.
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, UNITED STATES NUCLEAR REGUIATORY Cohh1SSION BOILING WATER REACTOR GENERIC FUNDAMENTALS EXAM SECTION
^~-
i' Please Print:
Name:
Facility:
ID Number:
INSTRUCTIONS TO CANDIDATE Use the answer sheet provided.
Each question has equal point value. The pa: sing grades require at least 80% on this part of the written licensing examination. All examination papers will be picked up 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the examination starts.
SECTION Questions
% of Total Score THERMODYNAMICS 1 - 28 COMPONENTS 29 - 72 REACT 0r. THEORY
- /3 - 100 TOTALS-l~e0 1*
All work done on this examination is my own.
I have neither given nor received.id.
Candidate's Si nature 5
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NRC l<ULES AND CVIDELINES FOR THE CENERIC WNDAMENTALS EXAMINATION l
During the. administration of this examination the following rules apply:
(1) Print your name in the blank provided on the cover sheet of the examination,
-(2) Fill in'the name of the facility you are acsuciated with.
s (3)
Fill in the.ID Number you were given at registration.
'(4) Three handouts are provided for your use during the examination, an Equations and Conversions sheet, instructions for filling cut the answer sheet. and Steam Table bocklets.
(L) Use only the answer sheet provided.
Credit will only be given for
- t answers marked on this sheet.
Follow the insttuctions for filling out the answer sheet.
s (6) Scrap paper will be provided for calculations.
(7) Any questions about an item on the exaoination should be directed to the examiner only.
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(8) Cheating on the examination will result in the automatic forfeiture of this examination.
Cheating could also ree 11t in severe penaltios.
(9) Restroom trips are limited. Only ONE examinee may leave the room at a i
time.
In order to avoid the appearance or possibility af cheating, avoid all contact with anyone outside of the examination room, s
i (10) After you have completed the examination, please sign the statemont on the cover sheet indicating thet the work is your own and you have not received or been given any assistance in completing the examination.
- s (11) Please turn in your examination materials answer theet on top followed by the exam booklet, then eesmin stion aids - steam table booklets, handouto and scrap paper used during the examination.
(12) After turning in your examination materials, leave the examinstion area, as-defined by the examinsr.
If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeited.
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- QUEST 10li:
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,, Y A difforential' pressure manometer filled with water is installed ceross an j
4' orifice in s: ventilation duct to determine the direction of airflow, as shown in the figure'belov'...What are the conditions in the. ventilation duet?-
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- A..
' P1 i'r greater than P2, and airflow is to the'right.
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P1 is'. graater than P2, and' attflow is to the lef t, i
C.
Pl!in,less than P?
@d airflow is to the right.
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'D.
P1 is less than P2, and airflow is'to the Icft.
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>E QUESTION:
2.' -
jGivenanto'peratingreactorat985psigandn-feedwaterinlettemperatureof h,400'F,whatwill\\boLfeedwatersubcooling?
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136.6 'F,'
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'aTho'. saturation pressure corresponding to 400 'F is:
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247.3 psia
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'B.
.262.0 psia
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BOILING UATER REACTOR CBIERIC FUNDMEETAIS IIANINATION 3
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QUESTION: 4 '.
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.The area of a steam jet air ejector (SJAE) Vaere the 1AVEST pressure exists is
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located at the:
e
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-A.'
throat of the noz :la.
l B '.
inlet to the nozzle.
C.
outlet of the nozzle.
1 D.
' suction piping from the-condenser to the SJAE.
QUESTION:
5.
l tE Condensate depression '(subcooling) is increased by increasing:
i t
A.
main turbine,1nad.
3 B.
the ci:culating water temperature, j
J C.
circulating water flow through the condenser.
D.
air leakage iat.o tae condenser.
QUESTION:
6.
E The thermodynamic cycle efficiency of a power plant is increased by:
x A.
decreasing the amour.t of condensate depression (subcooling).
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ma
]
q B.
removing a high-pressure feedwater heater from service.
l) 'l C.
Iowering condenser vacuum from 29 inches to 25 inchts.
(
m-h D.
. decreasing power from 1004 to 254.
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QUESTION:
7.
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LIf a valve closure suddenly atops fluid flow, the resulting piping system h}g,,E [.
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.' pre.sauro change is referred to as:
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A. 3 UR ; a.
) 1 cavitation.
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shutoff head.
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j '. J J[iy FORM B L - 4
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, QUESTION:
t The condition that would acs't likely cause cavitation of an operating pump is:
6-r l.} J A.
' lowering the suction telepe ature.
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'B.
throttling the pump: suction valve.
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C.
throttling the pump discharge valve.
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decreasing '.he pump speed.
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' QUESTION:
,9.
If two identical centrifugal pumps are operating in ZABALLEL, then:
L A.
the botal brake hersepower for the system is more than twice the horsepower of an individual pump.
s.
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B.
the total head for the system is the sum of the, two ' individual pump capacities.
L a'
C.
the. total capacity of the system is the sum of the, two individual pump L
capacities.
[
9 D,
the total brake horsepover for the system is the sum of the individual pump brake horsepowers.
1 t
3 y, 1
l QUESTION:
10.
'l.
Net positive suction head'(NPSH) is:
A.
^the differance bet. ween pump suction pressure and the saturation pressure of the fluid being, pumped.
B.
the difference.botween the total suction head and the pressure at the eye
.V '
'4 lof the paatp.
y.
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- f C.
'.thel amount of, suction pressure required to prevent cavitation, 1
p.
M'l:j,
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the difference between the pump suction pressure and the pump discharge
~l-pressure. ;
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1 QUEST 10N:
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A boilingyaeer reactor (BWR) is operating at a pressure of 1025 psia.
It.has a temperature of $30*F in the suction of the recirculatin6 pump ated an eleva-e
. tion head of 25 psia. Neglecting line losses, what is the net positive F N.> o suction head (NPSH)?
(..>
ll:
A.
148 psia t
r
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.7 B.
154 psia.
C.
165 psia D.
171 psia
/ QUESTION:
12.
4 Y)knacceptabicaethodtoreducewaterhammerinemergencycoreecolingsystems
/
is to:
l A.
maintain the system liquid full (vented).
B.
ensure minimum flow paths are mair*ained.
C.
maintain minimum NPSH requirements.
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.. D.
start pumps against shut off head.
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QUE$ TION: 13.
The heat transfer mechanist using direct contact transfer of kinetic energy from molecular motion 1_
il a la A'.
convection.
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.B.
.conduetion.
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C.
radiation.
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.D.
transmission.
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.FORN 5 i
L-14.
- QUESTION:
y,.
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LThe correct Order of boiling heat transfer mechanisms,.from the NOST EFFICIENT to the,LEAST EFFICIt.NT, is:
A.
stable film boiling.. transition boiling, nucleate boiling.
B.
nucleate boiling, stable film boiling, transition boiling.
L C.
transition boiling, nucleate boiling, stable l film boiling.
D.
nucleate boiling, transition boiling, stable film boiling.
?
QUESTION:
15.
c.
The uominant heat transfer mechanirm that occurs when film boiling is present is:
s I
A.
convection.
B.
radiation.
1 C.
conduction.
l t
D.
induction.
t QUESTION:
16.
The HIGHEST heat transfer from the fuel-cladding surface to the coolant channel is provided by:
A.
forced convection with subcooled coolant.(no boil.tng).
B.
natural convection with subcooled coolant (no boiling).
C.'
. natural convection with bulk boiling of coolant.
l D.
forced convection with nucleate boiling.
FORM B Page 5 of 34
- i..
se
3 OILING UATER REACTOR CEiGlRIC FUNDAMETALS EXAMINATION I
'L FORM B 1
m' QUESTION:
17.
j The ccrrect order of the heat transfer mechanisms existing in the boiling
~
water reactor (BWR) core (consider inlet to outlet flow) is:
)
A, subccoled nucleate boiling, single phase convection.: clug flow, annular flow.
B.
annular flow, singlephaseconvection,subcoolednucleateboilini,, slug flow.
C.
single phase convection, subcooled nucleate boiling, slur flow, annular flow.
D.
single phase convection, subcooled nucleate boiling, annular flow, slug flow.
QUESTION:
18.
Boiling improves heat transfer because:
A.
.it increases the effective thickness of the fluid film surrounding tl.e heat transfer surface.
B.
it increases the fluid velocity past the heated surface, which offsets the reouction in fluid film thickness at the heated surface.
C.
it increases the heat transfer from the heated surface due to the latent heat of condensation, as the steam bubbles collt"se at the heated surface.
D.
it produces agitation, which reduces the thickness of the fluid film and results in the latent heat of vaporization being removed, as the bubbles move away from the heated surface.
QUESTION:
19.
Select the statement which best describes transition (partial film) boiling.
A.
A small increase in delta-T (at the heat transfer and coolant interface) j causes increased steam blanketing and a reduction in heat flux.
B.
The tamperature of the boat transfer surface is so high that thermal p
radiative heat transfer becomes significant and heat flux increases.
l l
l C.
As the delta T increases, the increasing number of bubbles causos l
increased agitation and turbulence of the boundary 1syer consequently increasing heat flux.
D.
As the delta-T increases a few vapor bubbles are formed which may collapse when they enter into the bulk c; the fluid.
L FDRM B Page 6 of 34 l
l
BOILING WATER REACTOR CENERIC FUNDAMETAlf EKAMINATION FORM S QUESTION:
20.
The onset of transition boiling (OTB) is:
'A.
the area on a heat transfer curve where the most energy is added to the
- coolant, B.
the period when clad temperature fluctuates as the heat transfer.
coefficient alternates between a high value and c such lower value.
C.
the most effective means of heat transfer.
D.
the period when clad temperature restins constant as the heat transfer coefficient becomes negative.
QUESTION:
21.
The relationship between BUNDLE POWER and BUNDLE FLOW RESISTANCE characteristics is-A.
flow resistance decreates as the quality and two phast flow increase.
B.
_ prior to boiling, as bundle power increases, bundle flow decreases.
C.
flow resistance increases as the quality and void fraction increase.
D.
flow orifices minimize the undesirable effects that quality decrease produces on bundle flow, r
c QUESTION:
22.
Linear Heat Generation Rate (LHCR):
A.
is the ratio of the power produced in a given fuel bundle divided by total core thermal power.
B.
is the ratio of the average power per rod divided by the rod power at 100% power.
1 C.
is the sum of the power produced by all fuel rods in a given fuel bundle at a specific planar cross section.
is the sum of the power per unit area for each unit area of the fuel D..
cladding for a unit length of a fuel rod.
l FORM B Page 7 of 34
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- BOILING WATR REACTOR CENERIC FUNDAMETALS EKANINATION J 'a '.
w.
.y0RN B 4
1
-QUESTION; 23 j
..;c 1The fraction of the limiting power density (FLPD) is equal to:
A.
LHCR'lactual)
^ "
LHGR (design)-
3 E
B.
ATPF + RPF.
I C.
IZE APF 4
D.
.LHCR IImit CPR 1
h QUESTION:
24 Which one of the following psrameter changes will cause ar. increase in the critical power of a fuel bundle?'
A.
The subcooling of the coolant entering the bundle decreases.
=!
'B.
.The local peaking factor increases.
C.
The coolant flow through the bundle increases, i
D.
The axial power peak shifts from the bottom to the top'of the bundle.
QUESTION:
25.
Operating the reactor within limits defined by the maximum average planar linear heat generation rate (MAPLRGR) prevents:
A.
exceeding 1 percent plastic strain in the cladding.
B.
exceeding peak fuel temperature of 2200 'F.
C.
the onset of transition boiling in the upper core.
D.
exceeding a peak clad temperature of 2200
'F.
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FORN B Page 8 of 34 3
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h BOILING UATER REACTOR CEN'OLIC FUNDAMETA1A EKANIMATION
,PfAM B f,
b o, QUESTION:
26.
7Y'
- 3
'The' fuel bundle power that would cas.se the onset of transition. boiling at some point in the fuel bundle is'the:
t
.A.
technical specification limit.
[
B.
critical power.
t i'
C.
maximum fraction of limiting power density.
L
~ D.
maximum power density.
i pt E.
- QUESTION:
27.
4,
+
Tho' threshold power for Pellet. Clad Interaction (PCI) decreases as fuel exposure increases because:
e
' A.
heat-transfer capability is reduced by buildup of fission products and crud layers, s
B.
chemical embrittlement of cladding occurs due to fission product gases.
C.
pellet densification occurs due to fuel burnout.
D.
zirconium hydriding is reduced with fuel burnup.
QU' bT10N:
>28.
a The likelihood of brittle fracture failure of the reactor vessel is reduced by:
A.
increasing vessel age.
1 r
B.
reducing vessel pressure, C.
reducing vessel temperature.
D.
reducing gamma flux exposure.
t L
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FORM B Page 9 of 34 y
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4 - -
BOILINC WATER REACTOR CENERIC PUNDAMETAIA EXAMINATION PORN B i
QUESTION:
29.
Which QEE of the following correctly describes the operation of a safety valve installed'on a high pressure steam system?
]
l A.
A safety valve is initially lifted off its seat by system pressure, then is forced fully open by an air-operated piston, j
'B.
As system pressure increases to the safety set point, the pressure overcomes' spring force on the valve operator, causing the valve to open.
J i
C..
A safety valve will remain open until system pressure has been reduced to the pilot valvc actuation setpoint.
D.
. When the open safety valve has returned system pressure to the lifting set point, a combination of air and steam pressure above the valve disk' closes the valve.
QUESTION:
30.
Which of the following correctly describes the relief mode of operation for a safety relief valve (SRV)?
l A.
The SRV must be manually opened and manually closed using the control l
- switch, 1
B.
The SRV will automatically open, but must be reset by the operator before it will close.
l C.
The SRV will automatically open and close to relieve excess system pressure.
1 D.
The SRV must be manually opened but will automatically close to prevent system depressurization.
l 1
l l
l' FORM B Page 10 of 34 o
7 1 Gas ' s'>l
p BOILING WATER REACTOR CENERIC FUNDAMETALS EXAMINATION FORN B
~ QUESTION:
31.
. What precautions is applicable, when transferring a controller for a flow control valve from automatic to manual control?
A.
Verify that both the automatic and manual controller outputs are the same prior to transfer.
B.
Do not attempt to adjust the control signals, since the manual control system tracks the automatic signal and adjusting the signals could negate
.the automatic tracking.
C.
Verify that the manual controller output is slightly less than the automatic controller's to prevent flow overshoot on the transfer.
D.
Verify that the manual controller output is slightly higher than the automatic controller's to ensure that no loss of flow occurs on the
- transfer, 6-
- (
QUESTION:
32.
What may be damaged if an operator attempts to manually disengage the motor on a motor operated valve while the motor is operating?
A.
Limit switches B.
Valve seat C.
Torque switches D.
Clutch QUESTION:
33.
Emergency core cooling, systems (ECCS's) typically have testable check valves in the discharge lines from the pump to the vessel. How does the testable check valve operate?
A.
The valve is opened by flow and pressure from the discharge of the ECCS pump.
B.
Instrument air is applied to the valve operator when the ECCS system is shut down to close the valve and ensure no leak across the seat.
C.
The check valve cannot be opened unless the associated ECCS pump is running.
D.
An air solenoid admits air to the valve on system initiation to ensure that the valve opens.
1 FORM B Page 11 of 34
-- s v rwwwwwwims urumme um===..== = = = =vi PORN B QUESTION:
34 Which statement best describes the function and use of valve backseats?
I' A.
Valve backseats are provided to remove pressure from the packing and stuffing box and are the normal method used to isolate the stuffing box for valve repacking.
B.
Valve backseats are provided to remove pressure from the packing.and stuffing box and are only used when needed to prevent packing leakage.
C.
Valve backseats are provided as a back up in case the primary seat leaks and are normally used during plant operations.
D.
Valve backseats are provided as a back up in case the primary seat leaks and are only used when needed to prevent valves from leaking excessively.
~
QUESTION:
35.
Given the equation for mass flow rate:
m-pxAxv where a - mass flow rate (1bm/sec) p - density of flowing fluid (1bm/ft3)
A - cross section of channel of fluid (ft2) v - average velocity of flowing fluid (ft/sec)
What is the effect on indicated mass flow rate if the liquid being measured has air in solution?
A.
Indicated flow would be greater than actual flow.
B.
Indicated flow would be less than actual flow.
C.
Indicated flow is not affected by air in solution.
D.
The effect on indicated flow is unpredictable.
QUESTION:
36.
A leak develops in the high pressure side of a flow detector. What effect does that leak have en the flow indication of the detector?
A.
The measured delta P will decrease, causing indicated flow to decrease.
B.
The measured delta-P will decrease, causing indicated flow to increase.
C.
The measured delta-P will increase, causing indicated flow to decrease.
D.
The measured delta-P will increase, causing indicated flow to increase.
FORM B Page 12 of 34
m D
BOILING WATER REACTOR GENERIC MINDAMETA13 EKAMINATION FORM B p-QUESTION:
37.
What happens to a fluid as it passes through a venturi?
t A.
Pressure remains constant, but the velocity increases as the diameter of the venturi decreases.
L o
B.
Pressure increases, but the velocity decreases as the diameter of the venturi decreases.
C.
Pressure decreases, but the velocity remains constant as the diameter of the venturi increases.
D.
Pressure increases, but the velocity decreases as the diameter of the venturi increases.
QUESTION:
38.
It is necessary to density. compensate the main steam line flow indication because the measured change in pressure across the flow elements is:
l A.
directly proportional to the volueetric flow rate,.
B.
inversely proportional to the volumetric flow rate, j
1 C.
directly proportional to the mass flow rate.
D.
inversely proportional to the mass flow rate.
l' L
I QUESTION:
39.
l-What is the reason for the reference leg being connected to the reactor I
pressure vessel (RPV) instead of being filled by a water source independent of the RPV?
A.
To provide a vent path for the prevention of a reference leg rupture
~
l during a rapid RPV depressurization.
l B.
To alleviate the need for density compensation by r.ct,
, the reference leg at the same temperature as the variable leg.
l t
l C.
To make the indicated level proportional to the square root of'the l
differential pressure between the reference and variable legs for all l
reactor pressures.
D.
To provide compensation for the RPV pressure exerted on the variable leg.
FORM B Page 13 of 34
. BOILING WATER REACTOR CENERIC FUNDAMETAIJ EXAMINATION PORM B L.
r:
- QUESTION:
40.
p If the variable leg temperature of a differential pressure level cell is higher than the calibration conditions, what will the level instrument indicate?
i A.
Indicated reactor water level is higher than actual reactor water level, i
B.
Actual level if the reference leg temperature is at the calibration conditions C.
Actual level if the reference leg temperature is the same temperature as the variable leg D.
Indicated reactor water level is lower than actual reactor water level.
QUESTION:
41.
What vill the indication be when a level D/P cell fails (D/P - 0)?
A.
O of full range B.
50% of full range C.
75% of full range D.
100% of full range i
QUESTION:
42.
Which of the following correctly describes a characteristic of a thermocouple?
A.
Indication will fail high offscale with an open circuit.
B.
They are generally more accurate than resistance temperature detectors (RTDs).
C.
A junction between two dissimilar metals will generate a voltage
. proportional to temperature.
D.
A junction between two dissimilar metals will result in a change in electrical resistance proportional to temperature.
FORM B Page 14 of 34
v f
. BOII.ING WATER REACTOR CENERIC,FUNDMETALE EXAMINATION PORN B
-QUESTION: '43.-
t The' difference between the setpoint and the measured parameter in an automatic flow controller is called:
A.
gain.
B.-
bias.
C.
feedback.
D, error.
QUESTION:
44.
Which of the following valves is NOST LIKELY to be used with a throttling positioner?
A.
Stop valve B.
Globe valve C.
Cate valve D.
Butterfly valve QUESTION:
45.
The governor on an emergency diesel generator regulates the amount of fuel l
supplied to the diesel engine to:
l A.
increase engine speed as load increases.
g B.
increase generator voltage as load increases.
l l
C.
maintcin engine speed nearly constant as load changes.
l D.
maintain generator voltage nearly constant as load changes.
l l
l l
l l
l l
FORN B Page 15 of 34 l
l l
P r.U g...y.*
,'. BOILING WATER REACTOR CENERIC FUNDAMETALS EIANINATION
'.J PORM B 4
[)*
QUESTION:
46.
l Venting a centrifugal pump prior to operating it ensures that:
f A.
pump runout will not occur.
i B.'
pump internal corrosion is reduced.
C.
gas binding is reduced.
D.
starting load is minimized.
i QUESTION:
47.
=
I What would result from operating a motor driven centrifugal pump for extended periods of time with the discharge valve shut?
A.
No damage, since the pump and motor are designed to operate with the discharge valve shut B.
Pump overheating, cavitating, and ultimately pump failure C.
Excessive motor current, damage to motor windings, and ultimately motor failure D.
Pump and motor speeding excessively and tripping on high notor current QUESTION:
48.
A centrifugal pump is operating at rated speed with an output head of 240 psig. The speed of the pump is then decreased until the power consumption is 1/64 of its original value. What is the approximate new output head?
A.
3.75 psig
.B.
15 psig i
C.
30 psig D.
60 psig FORM B Page 16 of 34
\\
[
BOIL 1HG UATER REACTOR CENERIC FUNDMtETAIA EXAMINATION
,I,
FORM B l
'?
' QUESTION:
49.
What will increase reactor recirculation puap available net positive suction head?
(Assume all other parameters remain constant.)
A.
Lost of feedvater heating while at 806 power B.
Increase in reactor coolant te.7perature from 100 'F to 200 'T during a reactor startup 1
C.
Decrease in reactor pressure during a normal venctor shutdown D.
Decrease in reactor water from the normal level to just below the low level alarm level QUESTION:
50.
Wich one of the following items is HQI a characteristic of centrifugal pumps operating in series?
A.
The available net positive suction hesd (NPSH) of the second pump in the series is greater than the NPSH in a single pump system.
B.
The capacity for two pumps operating in series is limited by the capacity of the first pump in the series.
C.
The total head for two pumps operating in series is ap,troximatley twice the head for a single pump supplying the same capacity.
D.
The power required to supply two centrifugal pumps operating in series is less than twice the power required for each of the individual pumps.
QUESTION:
51.
What is caused by operating a motor-driven centrifugal pump under runout conditions?
A.
Pump f.silure due to excessive pump cavitation.
B.
No damage, since the pump and motor are designed to operate without failure under pump runout conditions.
C.
Motor failure due to excessive current being drawn through the motor windings.
D.
Pump failure due to overheating, caused by the increased impellor to.
casing friction.
FORM B Page 17 of 34
u tai h t ma im n >> t o o
]
p FORM B g;
QUESTION:
52.
i t.
LA single. speed centrifugal fire pump tckes suction on a storage tank and discharges through a flexible fire hose. Ubich of the'following correctly i
describes the response of the pump discharge flow rate?
A.
Remain constant as the elevation of the pump discharge piping is raised l'
B.
Increase as the elevation of the pump discharge piping is raised C.
Decrease as the level in the storage tank on the' pu.ap suction is lowered D.
Remain constant as the level in the storage tank on the pump suction is'
. lowered l
1 QUESTION:
$3.
What will occur by operating a positive displacement pump with insufficient net positive suction head?
A.
Slip B... Decreased pump speed C.
D.
Vapor binding QUESTION:
54, 1
For large electric motors, why must the number of starts over a period of time.
be limited?
A.
Protect the power supply cables from insulation breakdown due to high starting current B.
Protect the motor windings from overheating C.
Prevent motor thrust-bearing damage due to lack of lubrication D.
Prevent rotor seizure due to thermal expansion of the windings caused by high starting current PORM B Page 18 of 34
BOILING MATER REACTOR GBERIC FUlGWEETAIA ERANIllATION p'
FORN B ig QUESTION:. 55.
L t,,
Given the following conditions for a variable speed motor driven centrifugal pump:
t Flow rate = 2000 gpm
+
Motor current = 100 amperes
.i If the flow rate is increased to 4000 SPm, which one of the following' motor i
current values MOST CIDSELY approximates the actual value?
A.
200 amperes i
B.
400 amperes C.
800 amperes 4
[
D.
1600 amperes t
t QUESTION:
56.
Which of the following best describes the motor current itidications that would be observed during the start of a large A.C. motor at full load?
[
A.
Amps slowly increase to the full load value.
B.
Amps immediately increase to the full-load value.
E.
C.
Amps immediately increase to approximately three times the. full-load e
- 1 value and then decrease to the full. load value.
1 D.
Amps immediately increase to approximately six times the full-load value and then decrease to the full-load value.
QUESTION:
57.
Which of the following correctly describes the effects on generator excitation with the generator paralleled to the grid?
-A.
Increasing field current increases excitation and shifts power factor from lagging.toward leading.
l B.
Increasing field current increases excitation and shifts power factor I
from leading toward lagging.
L L
C.
Decreasing field current increases excitation and shifts power factor l;
from leading toward lagging.
l lI D.
Decreasing field current increases excitation and shifts power factor I
from leading toward lagging.
n PDRM B Page 19 of 34 l.k>
BOILING WATER REACTOR GENERIC MJNDANETALS EXAMINATION FORN &
I QUESTION:
58.
As steam (shell) and liquid '(tube) heat exchangers are put into service, the:
A.
steam side is valved in before the water side to minimize scale buildup l.
on the heat exchanger tubes.
B.
water side is valved in before the steam side to prevent thermal shock from occurring.
C, water side is valved in before the steam side to ensure adequate venting.
D.
steam side is valved in before the water side to ensure that the cooldown rate does not exceed 100 *F/hr.
QUESTION:
59.
Decreasing the temperature of a cooled system using a shell and tube heat exchanger is NORMALLi accomplished by:
A.
increasing the cooling system flow.
B.
increasing the cooled system flow.
C.
decreasin5 the cooling system flow.
D.
decreasing the cooled system flow.
QUESTION:
60.
Which of the following changes will DECREASE subcooling of the condensate water?
A.
Isolate one bay of the condenser circulating water system.
B.
Decrease circulating water temperature.
C.
Increase circulating water flow.
D.
Decrease the main turbine generator Megawatt load.
I FORM B Page 20 of 34 l
BOILING UATER REAC1M CENERIC FUNDAMETALS EEAMINATION w
f 4.
FORM B 1
D' QUESTION: '61.
[ "
During normal. reactor operation, a main condenser develops an air leak which decreases vacuu.n at a rate of 1 in Hg/ min. Which of the following plant parameters.would be the ELESI to :show an INCREASE because of this condition?
A.
Extraction steam flow B.
Cenerator megawatt output C.-
Circulating water. outlet temperature D.
Condensate temperature r
r QUESTION:
62.
-What is the saturation temperature for a boiling water reactor (BWR) operating at 920 psig ?
[Use steam tables.}
A.
532.6 'T l
B.
533.9 'F C.
536.5 'F D.'
538.4 'F
-QUESTION:
63.
Why should fouling of heat exchanger tubes in closed cooling water systems be MINIMIZED?
A.
To prevent excessive heat transfer rates.
B.
To prevent' the cooling water outlet temperature from exceeding design limits.
C.
To maximize the pressure the drop across the heat exchanger.
D.'
To maximize the heat transfer rate.
i l3 l
l 1
l FORM B Page 21 of 34 i
r
]
u UF
. BOILING WATER REAC1VR EENERIC FUNDAMETAIA ERANINATION
. 1 FORM B Mi iq' QUESTION:
64.-
1 Why'is proper venting of a shell and tube heat exchanger important?-
l A.
An air bubble reduces the heat transfer coefficient of the heat j
p exchanger.
I B.
'An air bubble causes pressure transients within'the tubes as heat load
[
changes.
C.
An air bubble will cause thermal shock as it moves through the heat 1
exchanger, j
D.
An air bubble will cause corrosion in the heat exchanger.
)
i i
i QUESTION:
65.
[
What is the. purpose of a mixed bed demineralizer?
A.
To remove both positively and negatively charged ions.
B.
To reduce the conductivity without affecting the pH of the water.
C.
To increase pH by reducing the number of positively charged. ions in the water.
D.
To increase the conductivity of the water to greater than 1.0 micromhos.
4 QUESTION:
66.
[
In a demineralizer, what adverse effect occurs due to channeling?
A.
Reduction of delta P across the demineralizer because the resin is essentially bypassed B.
Reduction in demineralization efficiency because the resin is essentially bypassed C.
Loss of resin due to agitation as a result of increased velocity through the demineralizer D.
Resin damage due to the increased velocity of fluid through the domineralizer 1
s
(:
L FORM B Page 22 of 34 l
l
~
e e-we-
-e
a,
a BOILINC UATER REACTOR CENERIC FUNDAMETAla EIANINATION 4-j.
FORM B
]
s?,:
QUESTION:
67.
]
.'d.
t The firstt indication of resin depletion in the effluent of. a demineralizer is:
)
c A.
a decrease in suspended solids, j
B.
an. increase in the conductivity, j
C.
a decrease in chlorides.
D.-
an increase in resin fines.
I-
. QUESTION:
68.
.I If the breaker control power is lost to a supply breaker for an operating pump motor, the breaker:
A.
will trip on undervoltage.
.B.
will remain closed until tripped locally by an operator.
C.
will remain closed unless a fault trip occurred.
D.
will remain closed until tripped remotely by an operator.
QUESTION:
69.
What is the definition of a thermal overload device?
s A.
A balanced circuit that compares actual current to a fixed overcurrent l
-signal which, when exceeded, trips a relay.
l B.
An in line thermal coil that, when subjected to a.high current, overheats and actuates a circuit interrupting device.
C.
A temperature monitor that senses the temperature of the operating equipment and trips the circuit breaker if the temperature exceeds preset limits.
l L
D.
An induction coil that generates a secondary current proportional to the L
primary current, closing the trip circuit contacts.
1l.
l' 1
L l'
e I
1 FORM B Page 23 of 34
i BOILING UATER REACTOR GENERIC PUNDAMETAIJ EIAMINATION FORM'8 e p*
_ QUESTION:
70.
s Never open or close a high voltage (greater than 750 volts) air break disconnect unless:
A.
the current flowing through it is approximately zero.
B.
the current flowing.through it is less t' san its design current carrying capability.
C.-
the circuit it is in is already open.
'l D.
a parallel path exists for current flow.
QUESTION:
71.
t If a generator output breaker is closed with generator frequency lower than i
grid frequency, what will result?
(Assume that no generator relay protection is actuated.)
A.
The generator will motorize.
B.
'The voltage of the generator will decrease to compensate for the lower frequency.
C.
The generator will accept too much load.
p D.
The entire connected system will operate at the frequency of the lowest l
L frequency-(the oncoming) generator.
l A
l QUESTION:
72.
For a circuit breaker placed in the test position, which of the following l
statements is correct?
A.
Control power is available to the breaker and functions normally to open and close the breaker.
B.
The test position can only be used to test a circuit breaker on a dead bus.
C.
The main power contacts remain connected to the load, but the breaker trips free when tested.
l D.
The test position disables the overload devices, allowing them to be set during normal operation.
1 i
FORM B Page 24 of 34 a.
L SOILINC UATER REACTOR CBIERIC FUNDMEETA1A EXAMINATJON l
p
.y roan s
-)
l
.g.
QUESTION:
73.
1 t:.'
1 1,
'i IThe term neutron generation time is MOST ACCURAT5LY defined as the average
.t; time between:
]
-l A.
neutron. absorption and subsequent fission.
B..
the production of a delayed neutron and subsequent neutron absorption.
[
C.
fission and subsequent production of a neutron.
i D.
neutron thermalization and subsequent neutron absorption.
QUESTION:
74.
Y,gg is HQI dependent on:
A.
core dimensions.
B.
core burnout.
C.
moderator to fuel ratio.
D.
installed neutron sources.
i
. QUESTION:
75.
The fractional change'in neutron population from one generation to the next is called:
A.
beta.
B.
Y,gg.
I C.
lambda.
~D.
reactivity.
l l
l l
l l-FORM B Page 25 of 34
f..
I BOILING WATER REACTOR GENERIC PUNDAMETALS EKAMINATION j.-
FORM B QUESTION:. 76.
What is the definition for DEIAYED NEUTRON MtACTION?
A.
Fraction of the total number of delayed neutrons produced from fission, born from delayed neutron precursors B.
Fraction of the total number of fast neutrons produced from fission, born frem delayed neutron precursors C.
Fraction of the total number of neutrons produced from fission, born from delayed neutron precursors D,
Fraction of the total number of thermal neutrons produced from fission, born from delayed neutron precursors.
QUESTION:
77.
After initial criticality, the reactor period is stabilized. The source range channels are repositioned so that the count rate is 100 cps.
Sufficient positive reactivity is added to establish a 120 second period. How much time-will it take for the count rate to increase to 10,000 cps with no additional operator action?
i A
1.2 minutes B.
4 minutes C.
'9.21 minutes D.
15.82 minutes QUESTION:
78.
During a reactor startup, the reactor is critical at 3000 counts per second.
A control rod is notched out, resulting in a doubling time of 85 seconds. How much time is required for the reactor to reach 888,000 cps?
A.
483 seconds B.
612 seconds C.
697 seconds D.
965 seconds l
FORM B Page 26 of 34
BOILING UATER REACTOR CENERIC FUNDMETAIA EKANINATION -
h
?:. ?
PORM B -
'l 5
.o
[4('
QUESTION:
79.
E
~
j The change in reactivity produced by a unit change in reactor coolant temperature,_ defines which reactivity coefficient?
i A.
Void B.
Moderator C.
Pouer 1
D.
Doppler QUESTION:
80.
Assume a reactor had been shut down for a shift, and shutdown cooling is in-service. Which'of the following coefficients of reactivity will act FIRST to l
change core reactivity upon a loss of shutdown cooling?
A.
Moderator temperature coefficient B.
Doppler coefficient-l h
C.
-Void coefficient D.
Pressure coefficient l
QUESTION:
81.
In regard to core parameters that affect control rod worth, which one of the following statements is correct?
i h
A.
control rod worth decreases in areas of increased flux due to rod shadowing, j
B.
control rod worth increases with an increase in voids l
C.
control rod worth increases witn an increase in fast neutron flux.
i' D.
control rod worth decreases when approaching end of core life (EOL)
FORM B Page 27 of 34
i BOILING WATER REACTOR CENERIC FUNDAMETALS EKANIMATION PDRM B y
6' QUESTION:
82.
i The reverse power effect or reverse reactivity effect occasionally observed when a shallow control rod is withdrawn one or two notches is due to i
relatively:
A.
large local power increase being offset by a moderator temperature-
'related power decrease.
B.
small local power decrease due to the shadowing effect of nearby control rods.
i
)
C.
small local power decrease due to increased local Doppler effeces.
D.
large local power increase being offset by a void related power decrease, QUESTION:
83.
4 What are the substances in the correct order, from LARGEST TO SMALLEST, of microscopic' cross section (thermal neutrons) for capture?
A.
U 235, H20, Xe 135 B.
U 235, Xe-135, H2O C.
Xe-135, U 235, H2O D.
Xe-135, H20, U 235 l
QUESTION:
84.
A reactoc has been shut down for 2 weeks after extended power operation. Uhat control rod movement is required to maintain 10 percent stable power immediately after startup?
A.
Small amounts of rod insertion to compensate for LPRM chamber depletion.
B.
Small amounts of rod withdrawal to compensate for Samarium buildup.
C.
Small amounts of rod insertion to compensate for installed poison burnout.
D.
Small amounts of rod withdrawal to compensate for Xenon buildup.
l l
FORM B Page 28 of 34
,--w.,
n r
a w,-
--,,v.,
w mw,.,
,~
.-,-,--,a
,ne,,-
+,
r q-s.
b
. BOILING UATER REAC1tlR CENERIC MINDANITALS EIANIMATION jy FORM B-
. QUESTION:' 85.
Following a reactor trip from a long-term, steady state,100 percent power run, the reactor is'to be taken critical. The calculated estimated critical conditions (position) are based on a XENON-FREE core. What is the shortest time.after the initial trip that this condition would exist?
A.
8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> B.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C.
40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> D.
70 to 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />
' QUESTION:
86.
If equilibrium reactor power level is increased from 50 percent to 100 percent, equilibrium xenon concentration will increase to a level that is:
A.
less than twice the 50 percent power concentration.
B.
equal to twice the 50 percent power concentration.
C.
more than twice the 50 percent power concentration.
D.
unpredictable unless the exact duration of operation at the two power.
levels is known.
QUESTION:
87.
A reactor has been operating at 50 percent power for a week when power is j
~
quickly ramped (over four hours) to 100 percent power. How would the Xenon
-~-
concentration'in the core respond?
A.
Decrease, then build up to a new equilibrium concentration in 40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> i
B.
Increase to a new equilibrium concentration in 40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> j
l C.
Decrease, then quickly build up to a new equilibrium concentration in l
eight to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> j
D.
Remain the same because Xenon concentration is independent of flux level
}
FORM B Page 29 of 34
._,, _ - ~, - _, -. -..
BOILING UATER REACTOR CINERIC FUNDMtETALS EXAMINATION.
5 Poax a QUESTION:
88.
What is the difference in peak xenon concentration following a reactor scram after 1 week at 100 percent power as compared to a scram after 1 week at 50 percent power?
i A.
The time to reach the peak is shorter after 100 percent power than after 50 percent power, due to the higher iodine decay rate, B.
The peak from 50 percent is of a smaller magnitude due to the lower Xenon s
burnout rate.
C.
The peaks are equal because the decay rate of iodine remains constant, D.
The peak from 100 percent power is of a larger magnitude, due to the larger initial iodine concentration, r
QUESTION:
89.
When comparing control rod worths during a reactor startup from 100 percent peak xenon and a reactor startup from xenon free conditions:
A.
center control rod worth will be higher during the peak xenon startup than during the xenon free startup.
B.
peripheral control rod worth will be higher during the peek xenon startup than during the xenon-free startup.
C.
both control rod worths will be the same regardless of core xenon conditions.
D.
it is impossible to determine how xenon will affect the worth of center L
and peripheral control rods.
QUESTION:
90.
Y L
A reactor has been operating at 100 percent power for about two weeks when power is reduced to 50 percent.
What is going to happen to the Xenon 135 i
concentration in the core?
l l
A.
There will be no change because Iodine concentration is constant.
1 B.
Initially Xenon will increase, than decrease to a new lower equilibrium value.
L l
l' C.
Initially Xenon will decrease, then increase to a new higher equilibrium i
value.
l l
D.
Xenon will decrease to a new equilibrium value.
l l
l FORM B Page 30 of 34
0,i t
BOILING WATER REACTOR GENERIC FUNDAMETALS EIANINATION FORN &
re o
}*
QUESTION:
91.
j 1
If a reacter that has operated at 100 percent power for ten days is shut down
[
rapidly, xenon concentration will:
L p
A.
slowly decay away to almost zero in three days,
~
B.
increase to a new equilibrium in three. days.
C.
peak in about a half day, then decay to almost zero in three days, D.
ramp down with reactor power.
)
?
QUESTION:
92..
What is the definition of the tern EURNABLE POISON 7 i
f-A.
Isotopes manufactured into the fuel with large scatter macroscopic cross I
sections.
F B.
Thermal neutron absorbing material added to the fuel, during the manufacturing process.
'C.
Neutron-absorber materials produced in the fuel by fast neutron absorption.
D.
Fast neutron absorbing material loaded into the upper third of the core to aid in slowing down neutrons.
v
-QUESTION:
93.
l approaches unity, which of the following During a reactor startup, as K statementsiscorrectforEDUAfgbSITIVEREACTIVITYADDITIONS?
[
1 A.
The changes in neutron population are larger as K,gg epproaches unity.
.B.
As the neutron population increases, the number of neutrons lost per generation decreases.
C.
The number of fast neutrons gained per generation increases more slowly as Keff approaches unity.
D.
A step increase in Keff increases the neutron population and therefore decreases the number of neutrons lost per generation.
l l
FORM B Page 31 of 34 i
~
s e
A BOILING' UATER REAC'!OR GENERIC FUNDMIETAIA EKANINATION
[.$
. k' FORM B F.
h\\I QUESTION:
94.
g
- t., '
.Durin6 reactor startup, critical rod position is NOT affected.by:
o A.
control rod worth.
B - source range. initial count rate.
C.;
fuel temperature.
D.
core age.
I s
i QUESTION:
95.
During a reactor.startup, as Keff approaches 1,0, it takes longer to reach an equilibrium neutron count rate due to the increased effect of:
A.
prompt neutrons, j
' B.
delayed neintrons.
l C.
fast neutrons.-
D.
slow neutrons.
l QUESTION:
96.
Assume a reactor is critical at a power level below the point of adding heat.
For an equal positive reactivity insertion, the reactor period would be:
A.
shorter if the core were xenon free.
B.
longer at EOL than at BOL.
~
C.
. shorter at EOL than at BOL.
D.
longer at higher moderator temperature.
T t
PDRK B Page 32 of 34 t
w
,s-s n--
m.e e -, - - - -ww--
fr~i S
f
> SOII.ING UATER REACitR CBIERIC PtBIDANETALS EKAMINATION
<o
.FORN &
' QUESTION:
9 7 '.
i For which one of the-following events will the Doppler coefficient act FIRST l
to counteract the reactivity addition to the core?
t A.
A control. rod drop during reactor power operation i
B.
The loss.of one feedwater heater (extraction steam isolated) during reactor power operation 1
O.
Tripping of the nain turbine at 45 percent reactor power b.
A safety relief valve opening during reactor power operation QUESTION:
98.
.A reactor is operating at 100 percent power and flow. Reactor power is i
reduced by driving control rods in.
(Recirculating pump speed remains
. constant.) What is the effect on core flow?
A.
Core flow will increase, due to the decrease in two-phase flow resistance.
B.
Core flow will remain constant, since reactor power does not affect core flow.
C.
Core flow will decrease, due to an increase in two-phase flow resistance.
D.
Core flow will increase, due to the increase in recirculation ratio.
?
QUESTION:
99.
What is the effect of isolating extrection steam to a high pressure feedwater heater while at 90 percent of rated power?
i A.
The core inlet subccoling remains the same while the turbine generator MWe output decreases.
B.
The core inlet subcooling and the reactor power (NWt) decrease.
C.
The reactor power (NWt) and the turbine generator MWe cutput remain the same.
D.
The core inlet subcooling increases and the turbine generator MWe output increases.
FORM B Page 33 of 34
p+ ',,g n
.b BOILING UATER REAC1tlE CEIGRIC FUNDMETA1A EIANINATION W - ' '
9c
- n '.
FORM B j
1
[ ' bI QUESTION:'100.-
W
. Shortly after a reactor trip, reactor power indicates 0.5% when a stable P ?'-
negarive startup-rate;(SUR) is attained. Reactor power will be reduced to p.
0.05% in approximately seconds.
{
4 l.
A.-
360 n
h.
B.
270 C.
180 i
.l
,?,
D.
90 t
b i
+
l l
l ln l
FORM B Page 34 of 34 1
1, l
l 1
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