Text

Forwards Forms of 891004 Generic Fundamentals Exam Section of Written Operator Licensing Exam,Including Answer Keys, Grading Results & Individual Answer Sheets for Each Examinees
	ML19327B544
Person / Time
Site:	Prairie Island
Issue date:	10/25/1989
From:	Weiss E; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Amundson T; NORTHERN STATES POWER CO.
References
	NUDOCS 8911010190
	Download: ML19327B544 (79)
	v • d • e

f e

i SE Q i

GCT t 5 1999 Docket No. 50-282 Docket No. 50-306 I

Northern States Power Company l

Prairie Island Nuclear Generating Plant ATTN:

T. Amundson Training Department 1660 Wakonade Drive West Welch, MN 55089

Dear Mr. Amundson:

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 Pu)11c Document Room (PDR). The results for individual examinees are exempt from disclosure; therefore, enclosures (3) av (4) will not be placed in the PDR.

Should you have any questions concerning this examination, please contact Mr. Paul Doyle at (301) 492-1047.

Sincerely.

l Original signed by:

Eric W. Weiss, Acting Chief Operations Branch l

l

Enclosures:

1 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

cc.w/ enclosures 1 and 2 only:

1 DCD/DCB(RIDS) l cc w/o enclosures:

P. Doyle, LOLB Joj R11 R

l Burdick cg W

10/'l 89

D ww, UNITED STATES NUCLEAR REGULATORY COMMISSION

.i

>. y' PRESSURIZED WATER REACTOR CENERIC TVNDAMENTALS EXAMINATION Please Print:

Name:

i Facility:

ID Number:

INSTRUCTIONS TO CANDIDATE Use the answer sheet provided.

Each question has equal point value. The passin& Stades require at least 80% on this part of the written licensing l

examination. All examination papers will be picked up 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after the examination starts.

f SECTION Questiont 4 of Total Score COMPONENTS 1

43 i

REACTOR THEORY 44 72 5

THERMODYNAMICS 73 100 TOTALS 100 l

All work done on this examination is my own.

I have neither given nor received aid, r

i Candidate's Signature h

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f l

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FORM A i

i l

3 RULES AND CUIDELINES ICR THE CENERIC FUNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:

(1) Print your name in the blank provided on the cover sheet of the examination.

l (2) Fill in the name of the facility you are associated with.

(3) Fill in the ID Number you were given at registration, j

(4) Three handouts are provided for your use during the examination, an Equations and Conversions sheet, instructions for filling out the answer sheet, and steam Table booklets.

l (5) Use only the answer sheet provided. Credit will only be given for i

answers marked on this sheet.

Follow the instructions for filling out the answer sheet.

(6) Scrap paper will be provided for calculations.

(7) Any questions about an ites on the examination should be directed to the examiner only.

(8) Cheating on the examination will result in the automatic forfeiture of this examination.

Cheating could also result in severe penalties.

(9) Restroom trips are limited. Only ONE examinee may leave the room at a l

time.

In order to avoid the appearance or possibility of cheating, avoid all contact with anyone outside of the examination room.

(10) After you have completed the examination, please sign the statement on j

the cover sheet indicating that the work is your own and you have not l

i received or been given any assistance in completing the examination.

(11) Please turn in your examination satsrials answer sheet on top followed by the exam booklet, then examination aids steam table booklets, handouts l

and scrap paper used during the examination.

l l

I l

(12) Af ter turning in your examination materials, leave the examination area, as defined by the examiner. If after leaving you are found i,n the

~

i examination area while the examination is in progress, your examination may be forfeited.

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[N' FRESSURIEED WATER REAC1tX GBIERIC FUNDMENTALS EXANIMATION

[

FORN A-

' QUESTION:.'1..

'osi primary ' purpose of a pressure relief valve is to:

i A.

maintain system flow..

s.

[)

'B.

maintain-system pressure, j

v C.

maintain system inte5rity, e

o.

(;;

D.

maintain-system temperature.

H

+

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QUESTION:

2.

I[ '

When'a discharge valve is opened to atmosphere, the-pressure on the upstream o

siue of the valve:will:'

A.

remain the same, and the pressure on the downstream side will ir. crease.

f

.B..

increase, and the pressure on the downstream side will remain the same.

C.

romain'the same, and the pressure on the downstream side will decrease.

l:

D.

decrease, and the pressure on the downteream side will remain the same.

(

i QUESTION:

3.

The function of a valve backseat is to:

j A.

isolate system' pressure from the packing and stuffing box to minimize K

packing leakage.

E B.

isolate system pressure from the packing and stuffing box for the pulpee*

of. valve repacking.

C.

provide a backup means of flow isolation in the event of primary seat f

leakage.

D.

provide a backup means of flow isolation in the event of a pipe break.

P i

FORM A Page 1 of 35

I r

PRESSURIEED WATER REACTOR CENERIC FUNDAMENTAIA EXAMINATION FORN A 4,.

QUESTION:

4.

After manually positioning a motor operated valve, how is the valve actuator re-engaged?

A.

Actuation of the torque switch B.

Manually pulling up on the manual declutch lever C.

Actuation of either the full open or full closed limit switch D.

Actuation of the valve actuator motor in either the open or closo direction QUESTION:

5.

To verify the position of a closed manual valve, the operator should operate the valve:

A.

to the fully open position,.then reclose it using normal force.

B.

in the closed direction using normal force.

C.

in the open direction until flow sounds are heard, then close the valve using manual force.

D.

in the closed direction until it stops, then close it an additional one half turn using normal force.

QUES'fl0N:

6.

Density compensation is used in flow instruments to change to l

1 A.

mass flow rate, volumetric flow rate B.

volumetric flow rate, mass flow rate C.

fluid pressure, volumetric flow rate D.

differential pressure, mass flow rate l

I l

l l

FORM A Page 2 of 35 l-L

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1 PRESSURIEED WATER REACTOR GENERIC FUNDMGMTA1A EEANIMATION i:;

FORM A i

4 j

QUESTION:

7. '

If the liquid flowing through a liquid flow rate sensor contains entrained voids.(gss or steam), indicated flow rate will be:

A.

erroneously high.

B.

~ erroneously low.

.e C.

unaffected.

l D.

fluctuating.

. QUESTION:

8.

If.the equalizing line on a differential pressure (D/P) flow detector is opened, the flow detector indication will:

A, increase slightly.

B.

decrease slightiy.

?

- C.

go to zero.

- D.

not change.

{

h QUESTION:

9.

Flow detectors (such as an orifice, flow nozzle, and venturi tube) measure flow rate using the principle that flow rate is:

A.

DIRECT 12f proportional to the differential pressure.

i B.

INVERSELY proportional to the differential pressure.

C.

DIRECTLY proportional to the square root of the differentia 1' pressure.

D.

INVERSELY proportional to the square root of the differential pressure.

),-

a FORM A Page 3 of 35

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PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EKAMINATION FORN A r

QUESTION:

10.

The pressure differential between a reference leg and a variable leg is:

A.-

DIRECTLY proportional to the height of the variable leg.

B.

IEEEEFELY proportional to the height of the variable leg.

C._

DIRECTLY proportional to the density of the reference leg.

D.

INVERSELY proportional to the temperature of the reference leg.

QUESTION:

11.

If the reference leg of a differential pressure level indicator experiences high ambient temperatute, indicated level will:

A.

read less than actual level.

3 B.

read greater than actual level, t

C.

equal the' actual level.

D.

slowly decrease to zero.

9 QUESTION:

12.

The level indication for a reference leg differential pressure level instrument will fail LQM as a result of:

A.

a break on the reference leg.

B.

a rupture of the diaphragm in the differential pressure cell.

C.

the reference leg flashing to steam.

l D.

a break on the variable icg.

1 1

a 1,

i l

l FORM A Page 4 of 35

FRESSURIEED WATER REACTOR GENERIC PUNDAMENTALS EKANINATION FORN A

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QUESTION: 13.

A resistance temperature detector (RTD) operates on the principle that the change in electrical resistance of:

A, two dissimilar metals is DIRECTLY proportional to the temperature change measured at their junction.

l B.

two dissimilar metals is INVERSELY proportional to the temperature change measured at their junction.

C.

a metal is DIRECTLY proportional to its change in temperature.

D.

a metal is INVERSELY proportional to its change in temperature.

QUESTION:

14.

Two differential pressure level transmitters are installed in a large tank.

If transmitter I is calibrated at 200 'F and transmitter II is calibrated at 100

'F, then at 150 'F:

A.

transmitter I will read greater than transmitter II.

'B.

transmitter II will read greater than transmitter I.

C.

transmitter I and II will read the same.

D.

it is impossible to predict how either transmitter will respond.

QUESTION:

15.

L Scintillation detectors operate on the principle of:

A.

photodisintegration.

B.

photokinesis.

C.

photomultiplication.

D.

photoionization.

FORM A Page 5 of 35

i l

i PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION FORN A I'

QUESTION:

16.

A BF3 proportional counter detects both neutrons and gammas. Which of the l

i following best describes the method used to eliminate the gamma contribution from the detector output?

A.

Two counters are used, one sensitive to neutron and gamma and the other i

sensitive to gamma only. The outputs are electrically opposed to cancel

.s -

the gamma induced currents and yield a neutron only signal for indication use.

B.

The BF3 proportional detector records neutron flux of sufficient intensity that the gamma signal is insignificant compared'to the neutron signal and yields a neutron only signal for indication use.

C.

Gamma induced detector pulses are of insufficient width to generate a significant log-level amplifier output. Neutron pulses are the only ones with sufficient width to yield a neutron only signal for indication use, l-D.

Neutron induced current pulses are significantly larger than those from gamma. The detector signal is applied to a circuit which filters out the smaller gamma pulses yielding a neutron-only signal for indication use, c

QUESTION:

17.

t The difference between the setpoint and the measured parameter in an automatic flow controller is called:

l A.

gain.

l l

B.

bias.

l C.

feedback.

i D.

error.

l l

QUESTION:

18.

A controller's output is typically insufficient to accurately drive a valve actuator. To overcome this problem, a control loop normally employs:

A.

a lead / lag unit.

B.

a regulator.

C.

a positioner.

D.

an amplifier unit.

FORM A Page 6 of 35

l FRESSURIEED WATER REACTOR CENERIC FUNDMENTALS MANINATION FORN A QUEST 10N: 19.

Why must an operator pay particular attention to auto / manual valve controllers l

1 eft in the manual mode?

A.-

The manual valve control is usually not stable compared to the automatic mode.

i B.

The valve position will no longer respond to changes in system parameters.

C.

The controlled parameters will no longer be controlled by the valve f

position.

D.

The valve can only be operated locally during this time, t

l QUESTION:

20, 1

What precautions must be observed when transferring a valve controller from the automatic mode to manual mode of control?

A.

Ensure that the proper offset is established between the automatic mode and manual mode.

B.

Ensure that the valve controller output signals are matched between automatic mode and manual mode.

l C.

Ensure that the valve controller stabilizes in the automatic mode'before l

l-complete 1y transferring to the manual mode of control.

D.

Ensure that the automatic valve controller signal is increasing before transferring to manual mode of control.

I l

l QUESTION:

21.

An indication of centrifugal pump cavitation is:

A.

pump motor amps pegged high.

l B.

pump discharge pressure indicating zero.

C.

pump motor amps oscillating.

D.

pump discharge pressure indicating shutoff head.

1 FORM A Page 7 of 35

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o LO PRESSURIEED WATER REAC1tlR CENERIC FUNDAMENTALS EKANIMATION s

l-FURN A p.

e QUESTION:

.22.

y.-

h The term " shutoff head' for a centrifugal pump indicates that it is pumping.

y at:

. A.

maximum capacity and minimum discharge head'.

B.

maximum capacity and eaximum discharge head.

C.

minimum capacity'and maximum discharge heed, p

g-.

, D.

minimum capacity and minimum discharge head.

. QUESTION:

23.

Operating a motor driven centrifugal pump for extended periods of time with no i

l.

flow through the pump will cause:

A.. pump failure from overspeed.

B.

pump failure from overheating.

C.

motor failure from overspeed.

D.

motor failure from overheating, l

QUESTION:

24.

SHUTIING the discharge valve on an operating centrifugal pump will cause the MOTOR AMPS to and the pump plS 2 &RGE FRESSUEE to l-A.

increase, increase B.

decrease, increase

~

C.

increase, decrease l

l i

D.

decrease, decrease

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l

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PORM A Page 8 of 35 1

1..

1

I

- PRESSURIZED WATER REAC'!OR GENERIC FUNDMENTALS EIANINATION j

,S FORN A

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QUESTION:

25.

j

' ~

i s

.o If the speed of a positive. displacement pump is increased, the available not q

positive suction head (NPSH) will and the probability of 1

, cavitation will A..

increase, it. crease B.

decrease, decrease 3

C.

increase, decrease D.

decrease, increase i

t.

h QUESTION:

26.

Reactor coolant pump motor amps will if the rotor is ] GEED and.

[

the motor speed will

_ if the rotor Stig&BS.

.l A.

increase, increase B.

increase, decrease C.

decrease, increase D.

decrease, decrease 4

t l.

QUESTION:

27.

If the generator bearings on a motor generator overheat then:

I-A.

the generator voltage will increase.

1 :.

B.

the generator windings will overheat.

C.

the moto current will decrease.

J' l

D.

the motor windings will overheat.

+

FORM A Page 9 of 35

4 PRES $URIZED' WATER REACTOR GENERIC FUNDAMENTAIA EIANINATION

)

PORN A t

1

. '.L' QUESTION:

28.

1 if the speed of a variable speed centrifugal. pump is increased to cause pump flow; rate. to double, pump motor current will:

A.

.romain constant.

B ~.

increase two fold (double),

j C.

increase four fold.

l D.

. increase eight fold.

)

QUESTION:

29.

The starting current in an A.C. motor is significantly higher than the 1

' full load running current because:

A.

starting torque is lower than running torque.

[

B' starting torque is higher than running torque.

C.

rotor current during start is higher than running current.

D.-

rotor current durinS start is lower than running current.

i QUESTION:

'30.

-The number of starts for an' electric motor in a given period of time should be limited because:

'A.

overheating of the windings can occur.

l B.

. excessive torque is generated during motor start.

C.

' running current is much hi her than starting current.

5 D.

motors are normally started under full load conditions.

t h

t FORM A Page 10 of 35

f n:

r FRESSURIEED WATER REACTOR GENERIC FUNDMENTAIA EEAMINATION 1

FURN A

..i

' QUESTION:.

31.-

)

,.4..

I Severe stress in.a mechanical component, induced by. a sudden, unequally.

distributed temperature' reduction is a description of:

A..

heat stress.

l J

I

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B.

. thermal shock.

C.

thermal strain.

.D,

' heat' strain.-

l

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l

.UESTION:

32.

Q

.s Tube fouling in a heat exchanger causes heat transfer to decrease by:

A.

reducing fluid velocity on the shell side of the exchanger.-

B.

increasing flow rate through'the tube side of the exchanger.

C.. ' reducing the overall (total) heat transfer coefficient.

D. increasing'the overall'(total) heat transfer coefficient.

l-t QUESTION:

3 3 ',

' Borsted water is flowing through the tubes of a heat exchanger being cooled by fresh water; The shell side pressure is less than tube side pressure. What will occur as a result of a tube failure?

A.

Depletion of borated water inventory.

1 B.

Depletion of cooling water inventory.

~

C.

Dilution of the borated water system.

D.

Shell pressure will decrease.

a,.>

FORM A Page 11 of 35

D -- -

F' L

PRESSURIZED WATER REACTOR' GENERIC PUNDAMENTALS EXANINATION 4-FORM A

[ :,.

QUESTION:

34.

What is the reason for bypassing a domineralizer due to high temperature?

l.. '

A.

Resins expand and restrict flow through the domineralizer.

B.

-The domineralizer decontamination factor is dramatica11y' increased.

C.

Organic compounds used as resins will decompose, D.

The creation of preferential flowpath through the domineralizer will c

occur.

V QUESTION:

35.

In the event of a system crud burst, what adverse effect does the crud burst have on domineralizar operation?

A.

Increases pressure drop across domineralizer B.

. Increases flow rate through domineralizer i

'l C.

Increases domineralizer outlet conductivity D.

Increases domineralizer inlet pH i

QUESTION:

36.

1 I

' Boron concentration in the reactor (primary) coolant system has been

. decreasing steadily at approximately 10 ppa per hour while using the deborating domineralizer. After several hours, the rate decreases to 2 ppm per hour. What is a possible cause for the change in deboration rate?

A.

Temperature of the coolant passing through the domineralizer has decreased.

L B.

pH of the coolant has increased significantly.

I' Flow through the deborating resins has increased sharply.

C.

D.

Deborating resins have become boron saturated.

FORM A Page 12 of 35 11

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PRESSURIZED WATER REAC1TIR CENERIC FUNDAMENTA1A EIANIMATION j

,y PORN A i

1 n

U QUESTION:-

37.-

q y

To'de energize a component and its associated control and indication circuits, j

)

y the component circuit breaker should be' I

A.

racked in and tagged in open position.

j J

B.

racked in and tagged in closed position.

C.

racked out'and' tagged in racked out. position.

I D... in the. test position and tagged in test.

1

>c 3

r QUESTION:

38.

2 To ensure reliable local breaker indication is being provided the must-be reset after breaker operation..

A.

OPEN/ CLOSED mechanical flag

' B.

' OPEN/ CLOSED indicating lights L

l lC.

Overcurrent trip flag i

D.-

Spring CHARCE/DISCHARCE flag I

QUESTION:

39..

,.l A circuit breaker thermal overload device:

r L.

A..

compares actual current to a fixed overcurrent setpoint that is equated l

I to temperature and actuates a trip relay.

J B.

when subjected to high current, overheats and actuates a circuit-interrupting device.

C.

senses operating equipment temperature and trips protective circuits at preset limits.

i D.

is an induction coil that produces a secondary current proportional to the primary current.

PORN A Page 13 of 35

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i FRESSURIEED WATER REACTOR OENERIC FUNDAMENTALS B AMINATION PURN A

. QUESTION:

40.

[

Loss of circuit breaker control power will cause:

A.

breaker line voltage to be zero regardless of actual breaker position.

I B.

the remote breaker position to indicate closed regardless of actual breaker position.

C.

inability to operate the breaker locally and remotely, i

f D.

' failure of the close spring to charge following local tripping of tte

breaker, QUESTION:

41.

If a de energized bus is not unloaded prior to closing the output breaker of a i

three-phase generator onto the bus, then:

A.

an overvoltage condition will occur on the bus.

B.

an overcurrent condition will occur on the generator.

C.

an overvoltage condition will occur between generator phases.

D.

generator undervoltage relay actuation will occur.

1 I

QUESTION:

42.

(

[

Which of the following statements is correct concerning the use of disconnect l

switches?

I l

A.

Disconnects should be limited to normal load current interruption.

1 i

B.

Disconnects may be used to isolate transformers in an unloadqd network.

C.

Disconnects are similar to oil circuit breakers, but are manually operated.

D.

Disconnects must be closed with caution when under load because of possible arcing.

FORM A Page 14 of 35

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!n.. ' h PRES $URIEED WATER REAC1tIR GENERIC FUNDMENTALS EEANIMATION.

L FURN A QUESTION:

43.:

Closing a generator output breaker with the generator. frequency much less than i.-

grid frequency will cause the generator to trip on:

c l

A..

reverse power.

O B.,

overvoltage.

<f

c-C.

overcurrent.

r r

R D.

'overspeed.

L

. QUESTION:

44.

1 V'

The operator has just pulled control rods and changed the effective multipli-i cation factor (K,fg)'from 0.998 to 1.002. The reactor is:'

A '.

prompt critical 3

B.

supercritical l

l C.

exactly critical D.-

suberitical l

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1 l.l-FORM A Page 15 of 35

1

,f PRESSURIEED WATER REACTVR CENERIC FUNDMENTA1A EIANIMATICM FORN A n.

QUESTION:

45.-

The ratio'of:the number of neutrons in one generation to the number of

- neutrons in the previous generation is the:

<A.

effective multiplication factor B..

fast fission factor C.

neutron non leakage factor i

D..

neutron reproduction. factor i

QUESTION:

46.

Reactivity.is defined as the:-

L.

A.

fractional change in neutron population per generation.

]

B.

number of neutrons by which neutron population changes per generation.

.t C.

rate of change of reactor power in neutrons per second.

D.

change in the number of neutrons per second that causes a fission event.

)

i QUESTION:- 47.

l i

A given amount of positive reactivity is added to a critical reactor in the

source (startup) range. The amount added is less than the average effective delayed neutron fraction. Which of the following will have a significant effect on the magnitude of the stable startup rate achieved for this addition?

(

A.

Prompt neutron lifetime i

l B.

Fuel temperature coefficient i

C.

Average effective decay constant

?

D.

Moderator temperature coefficient s

I r

FORM A Page 16 of 35 e

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i FRESSURIEED WATER REACTOR CENERIC FUNDAMENTALS EIANINATION p, y,-

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. QUESTION: 48; j

h is l

Over core life the production of. plutonium isotopes with delayed neutron kl fractions' than uranium delayed neutron fractions will cause j

~ reactor power. transients to be near the end of core life.

r

)

A.

'less; faster-i B.

less, slower l

E C.

greater, faster D.-

greater, slower.

t.

QUESTION:

49..

t1 l-An installed neutron source:

.A.

maintains the production of neutrons high enough to allow the reactor to achieve criticality.

i B.-

provides a means to allow reactivity changes to occur in a suberitical

reactor, e

C.

generates a sufficient neutron population to start the fission process i

L and initiato suberitical multiplication.

t D.

provides a neutron level that is detectable on the source range nuclear i

instrurantation.

l-QUESTION:

50.

Why does increasing reactor coolant boron concentration cause the moderator temperature coefficient to become less negative?

l A.

Reactor coolant temperature increases result in a larger increase in the L

thermal utilization factor.

B.

Reactor coolant temperature increases result in an increase in the resonance escape probability.

~

C.

Reactor coolant temperature increases result in an increase in the total jc non leakage probability.

D.

The change in resonance escape probability dominates the change in the j

thermal utilization factor.

FORM A Page 17 of 35

f

.i FRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EIAMINATION FOP.M A 4

. QUESTION:

51.

Why does the fuel temperature (Doppler) coefficient becomes less negative at higher fuel temperatures?

A.

As reactor power increases, the rate of increase in the fuel temperature diminishes.

B..

Neutrons. penetrate deeper into the fuel, resulting in an increase in the fast fission factor.

C.

The amount of self shielding increases, resulting in less neutron absorption by the inner fuel.

i D.

The amount of Doppler broadening per degree change in fuel temperature diminishes.

QUESTION:

52.

A reactivity coefficient measures-change while a reactivity defect (deficit) measures a change in reactivity due to a change in the measured parameter.

A.

An integrated, total B.

A rate of, differential s

C.

A differentini, total F

D.

A total, differential t

QUESTION:

53.

During power operation, while changing power level, core reactivity is affected most quickly by:

A.

boron concentration adjustments.

B.

power defect (deficit).

C.

xenon transients.

D.

fuel depletion.

FORM A Page 18 of 35

1 4

-PRESSURIZED WATER REAC1tMt CENERIC FUNDAMENTA13 EKANINATION FORN A

]

- QUESTION:

54..

)

J As moderator temperature increases, the magnitude of differential rod (CEA) worth increases because:

A.

decreased moderator density causes more neutron leakage out of the core, f

B.

moderator temperature coefficient decreases, causing decreased

'i competition.

C.

fuel temperature increases, decreasing neutron absorption in fuel.

D.

decreased moderator density increases neutron migration length, c

QUESTION:

55.

Control rod (CEA) bank overlap:

A.

provides a more uniform differential rod (CEA) worth r.nd axial flux distribution..

l B.

provides a more uniform differential rod (CEA) worth and allow dampening of Xenon induced flux oscillations.

e r

C.

ensures that all rods (CEAs) remain within the allowable tolerance between their individual position indicators and their group counters and to ensure rod (CEA) insertion limits are not exceeded.

D.

ensures that all rods (CEAs) remain within their allowable tolerance between individual position indicators and their group counters and to I

provide a more uniform axial flux distribution.

l QUESTION:

56.

l The basis for the maximum power density (kw/ft) power limit is tot A.

prevent fuel clad melt.

l B.

prevent fuel pellet melt.

C.

limit bulk coolant temperature.

l D.

prevent nucleate boiling.

1' 1

FORM A Page 19 of 35

)

l FRESSURIEED WATER REAC'!UK GENERIC FUNDAMENTA1A EKANINATION j

FORN A y

QUESTION:

57.

The control rod insertion limits are power level dependent because the

'f magnitude of:

1 A.

control rod worth decreases as power increases.

-}

B.

power defect increases as power increases.

C.

Doppler (fuel temperature) coefficient decreases as power increases.

-i D.

moderator temperature coefficient increases as power increases.

QUESTION:

58.

Fission products that have substantial neutron capture cross sections are:

1 A.

excited fission products.

B.

fission product daughter.

C.

radioactive fission products.

1 D.

fission product poisons.

t I

QUESTION:

59.

f Following a reactor trip from sustained high power operation, Xenon 135 concentration in the reactor will:

A.

decrease because Xenon is produced directly from fission.

B.

increase due to the decay of Iodine already in the core.

C.

remain the same because the decay of Iodine and Xenon balanca each other out.

D.

decrease immediately, then slowly increase due to the differences in the I

half-lives of Iodine and Xenon, s

l-i l

l FORM A Page 20 of 35

<d FRRSSURIEED WATER REAC1tlR CENWLIC FUNDAMENTAIJ IIANIMATION j

FURN A.

?

QUESTION:: 60.

]

Following a reactor trip from sustained hi h Power operation, the major j

5 Xenon 135 removal process is:

(

A..

ion exchange.

l-B..

beta decay.

i C.

' neutron capture.

D.

alpha decay.

QUESTION:

61.

A' reactor has been operating at 50 percent power for 7 days when power is ramped to 100 percent over a four hour period.

The new equilibrium Xenon value wil3:

s A.

be_twice the 50 percent value.

i B.

be less than twice-the 50 percent value.

I l

C.

be more than twice the 50 percent value.

D.

remain the same since it is independent of power.

i QUESTION:

62.

i Slow changes in ar.ial power distribution in a reactor that has operated at a steady state power for a long time can be caused by:

.i A.

Xenon peaking.

B.

Xenon override.

i C.

Xenon burnup.

D.

Xenon oscillation.

PORN A Page 21 of 35 w-.

e l

PRESSURIEED WATER REAC1tNL GENERIC FUNDAMENTAIA EEAMINATION -

]

- 'i FORN A j

. QUESTION:

63.

' A reactor that has been. operating at rated power for about two. weeks reduces

]

power to 50 percent. Xe 135 will reach's new equilibrium condition in j

hours.

A.

-8 to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ' I

~

I B.

20 to 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months C.

30 to 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months

)

' D.-

40 to 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months .

QUESTION: 64 L

The reactor is near the end of its operating cycle.

In order to stay.

l-critical, power and temperature have been allowed to "coastdown." Why is boron uo longer used to compenrate for fuel depletion?

A.

Boron concentration approaches zero and requires excessive amounts of water to dilute.

E D

B.

The differential boron worth has decreased below its useable point.

h-C.

The boron in the coolant has been depleted due to neutron absorption.

D.

"Coastdown" is preferred due to fuel conditioning limitations.

QUESTION:

65.

While withdrawing control rods during an approach to criticality, the count rate doubles. What will occur if the same amount of reactivity that caused the first doubling is added again?

A.

Count rate will increase slightly.

f i

L B.

Count rate will double.

L L'

C.

The reactor will remain subcritical, j

~

l D.

The reactor will be critical or slightly supercritical.

l FORM A Page 22 of 35 o

e

~

4 FRESSURIEED WATER REACTOR CENERIC FUNDAIGlNTALS EIANIMATION FORN A

' QUESTION:

66.

.s.:

In a reactor with a source, a non changing neutron flux over a few minutes is

- indicative of criticality or:.

A..

the point of adding heat.

B.

supercriticality.

q l

. C.

suberiticality.

D.

equilibrium subcritical coant rate, j

QUESTION:

67.

At EOL, critical rod.(CEA) position h' as been calculated for a reactor startup four hours after's trip from 100 percent power equilibrium conditions. The actual critical rod (CEA) position will be LOWER than.the predicted critical i

rod (CEA). position if:

A.

the startup is delayed until eight hours after the trip, t

~ B.

the. steam dump pressure setpoint is lowered by 100 psi prior to reactor l

startup.

C.

actual boron concentration is 10 ppm more than the assumed boron concentration.

D.

one control rod (CEA) remains fully inserted during the approach to criticality.

QUESTION:

68.

Withk[f-0.985,howmuchreactivitymustbeaddedtomakethereactor criticI A.

1,480 pcm (1.48% delta-k/k)

B.

1,500 pcm (1.50s delta k/k)

C.

1,520 pcm (1,52% delta k/k)

D.

1,540 pcm (1.54% delta k/k)

FORM A Page 23 of 35 c

- - ~.... - -

t

' '.1 PRRSSURIEED WATER REACTVR CENERIC FUNDMODITALS EIANIMATION FORM A F

QUESTION: 69.

I i

If, during a reactor startup, the startup rate is constant.and positive l

without any further reactivity addition, then the reactor is:

i A.

critical'.

B.

supercritical.

C.

suberitical.-

D.

prompt critical.

'I QUESTION:

70.

Civen a critical reactor operating below the point of adding heat. What reactivity effects are associated with reaching the point of adding heat?

A.

.There are no reactivity effects since the reactor is critical.

B.

.The increase in fuel temperature will begin to create a positive reactivity effect.

C.

The decrease in fuel temperature will begin to create a negative

)

reactivity effect.

D.

The increase in fuel temperature will begin to create a negative reactivity effect.

QUESTION:

71.

i Shortly after a reactor trip reactor power indicates 0.5 percent where a e

stable negative SUR is attained. ' Reactor power will be reduced to 0.05 percent in approximately seconds.

A.

360 B.

270 C.

180 D.

90 PORM A Page 24 of 35

e PRESSURIEED WATER REAC19t GENERIC FUNDAIGNTALS EIANINATION--

'e FORM A c ;,

. QUESTION: 172, e

The major reason boron is used in a reactor is to permit:

A.

a reduction ~in the shutdown margin.

B.-

an increase in.the amount of control rods (CEAs) installed.

c.

C.

an increase in core life.

i D.

a reduction in the effect of resonance capture.

-)

I t

c s

b 1

i FORM A Page 25 of 35

b o

7. J PRESSIRIZED WATER REAC'!VR GENERIC FUNDAMENTA1A ERANINATION FORM A QUESTION:

73..

a:. -

fl

' An atmospheric pressure of 15 psia equals:

A.'.

30 psig.-

-~

(

B.

- 15 psig.

C.

5 psig.

D.-

O psig.

c QUESTION:

74.

Condensate depression is defined as:.

A.-

cooling the condensate below its saturation temperature.

s B..

maintaining the condensate at a constant temperature throughout the system.

C.

ensuring that the condensate is below the level.cf the hotwell pumps.

l D,

cooling the condensate to the point of saturation.

e l

- QUESTION:

75.

What is the reactor coolant system subcooling for Tave - 400*F and pressurizer i

pressure - 1,000 psia?

i i

A.

. 75'F f.

I' B.

- 100'F C.

125'F I

D.

145'F l:

1 1/.

I 1

l' l

l l

l FORM A Page 26 of 35 d1

-w,t gr w

-g* w tg

,,*--wwv.,.--

y,--,-y-g4.,w-w-wi-yg-, - - -- - -,,-

wy-<m-w u-

,-w,,.-y-

--w-ey-,wwe.,ww e

e -w waw-w,y

==

w, w

n-w,--w-

-e

/

-PRESSURIZEDWATERREACTORdENERICFUNDAMENTALSEIANINATION A

FORM A' QUESTION:

76.

The plant is maintained at 2,000 psia with a pressurizsr temperature of 636'F.

o A pressurizer safety relief valve is leaking to a collection tank which is being held at'10 psig. What is the temperature of the fluid downstream of the relief valve?

A.

280*F t

B.

240'F C.

190*F

'D.

'170'F s

QUESTION:

77.

Overall plant efficiency will DEGRE&SI if:

A.

the steam quality'is increased by removing moisture from the steam prior to entering the turbine.

i B,

the temperature of the feedwater entering the steam generator is increased.

T C.

the amount of condensate depression (subcooling) in the main condenser is

-decreased.

D, the tempercture of the steam at the turbine inlet is decreased.

l l'

(

QUESTION:

78.

l I

The possibility of a water hammer is MINIMIZED by:

t A.

changing valve positions as rapidly as possible.

B.

starting centrifugal pumps with the discharge valve fully open.

i C.

starting positive displacement pumps with the discharge valve closed, j

1 e

,3 I'

D.

venting systems prior to starting centrifugal pumps.

Il l

l t>

1 PORM A Page 27 of 35

I l g.[$

'FRESSURIEED WATER' REACTOR EENERIC' PUNDAMENTA1A EIANIMATION i

FORM A IND

. QUESTION:

79.

l 1

s,

}"i Cavitation in an oper. ming pump may be caused by:

,l c

A'-

lowering the suction temperature.

i

- B.-

' throttling.the pump suction valve.

?,

. C, throttling the= pump discharge valve.

D.:

increasing the pump discharge' pressure.

1

'.c s

[.

QUESTION:

80.

.The piping system pressure change caused by suddenly stopping fluid flow is I;

- referred to as:

A.

cavitation.

B.-

shutoff head.

.f C.

water hammer.

D.-

flow head,

-(

QUESTION:

81.

- If a~ flow measuring instrument is BQI density compensated, then indicated mass flow rate will be:

A the same as actual mass flow rate with a change in temperature of the fluid.

o r

B.

greater than actual mass flow rate with a decrease in temperature of the l

1 0

fluid.

' C.

less than actual mass flow rate with a decrease in temperature of the I

fluid.

D.

less'than actual mass flow rate with an increase in temperature of the e

fluid.

i s

o i

'i FORK A Page 28 of 35

>i

FREssURIEED nlATER REAC1tlR CENE3t1C FUNDANDf7A1A EIANIMATICII PORN A l

9 "L.

QUESTION:

82.

i operating two pumps in paralle.1 instead of operating a single pump will result in:

I A.

a large increase in system head and the same flow rate.

i B.

the same system head and a small increase in flow rats.

i

/

C.

a small increase in systen head and a large increase in flow rate.

D.

a decrease in systen head and a large increase in flow rate.

l QUESTION:

83.

j Excessive amounts of entrained gases passing through a single. phase (liquid)

)

hoat exchar.ser is 3pfDESIRAR12 because:

j A.

flow blockage can occur in the heat exchanger.

B.

the laminar layer will increase in the heat exchanger.

t C.

the heat transfer coefficient will increase in the heat exchanser.

i D,

the temperature difference across the tubes will decrease through the heat exchanger.

l t

QUESTION:

84.

In a two loop pressurized water reactor, feedvr.tr flow to each steaa gwrator is 3.3 x 10 lba/hr at an enthalpy of Ofr BTU /lba. Se steam exiting l

each steam generator is at 800 psia with 1006 stean quality.

Ignoring blowdown and pump heat, what is the core thermal power?

l A.

3,411 Wt 1

l t

I 2.

2.915 Wt C.

2.212 We t

D.

1,509 We i

1 PORM A Page 29 of 35

PRESSURIEED WATWL REACTOR GENERIC FUNDAMENTA12 EIANIMTICH FORN A i

i QUESTION:

'85.

i Why does nucleate boiling improve heat transfer in the core?

I l

A.

The formation of steam bubbles at nucleation sites on the fuel clad l

allows nore heat to be transferred by conduction, j

B.

Hett is removed from the fuel rod as both sensible heat and latent heat f

of vaperization, and the motion of the steam bubbles cause rapid mixing of the coolant, C.

Heat is removed from the fuel rod as both sensible heat and latent heat i

of condensation, and the heat is transferred directly to the coolant by i

radiative heat transfer.

D.

The formation of steam bubbles at nucleation sites on the fuel clad i

reduces coolant flow in that area and allows more heat to be transferred by convection.

l QUESTION:

86.

I Subcooled nucleate boiling is occurring along a heated surface. The heat flux l

is then increased slightly. What will be the effect on the delta T between i

the surface and the fluid?

l A.

Large increase in delta T because of steam blanketing l

B.

Large increase in delta T causing radiative heat transfer to become significant C.

Small increase in delta T because of steam blanketing D.

Small increase in delta T as vapor bubbles form and collapse QUESTION:

87.

t i

What parameter change would move the plant farther away from the e,ritical heat i

flux?

A.

Dovrease pressuriser pressure 7

r B.

Decrease reactor coolant flow I

C.

Decrease reactor power D.

Increase reactor coolant temperature 3

i FORM A Page 30 of 35

- ~ - - -.

FRESSURIEED WATER REACitIR CENERIC FUNDMENTALS EKMIINATION t

NA

[

QUESTION:

88.

l Film boiling is:

A.

heat transfer through a vapor blanket that covers the fuel cladding.

B.

heat transfer being accomplished witin no phase change.

C.

the most efficient method of boiling heat transfer.

D.

heat transfer throuBh an oxide film on the cladding.

t I

QUESTION:

89.

The departure from nucleate boiling ratio (DNBR) is defined as.

A.

the actual heat flux divided by the critical heat flux at any point along

{

a fuel rod.

B.

the critical heat flux divided by the actual heat flux at any point along l

a fuel rod.

j I

C.

the et,re thermal power divided by the total reactor coolant mass flow l

rate.

D.

the number of coolant channels that have reached DNB divided by the number of coolant channels that are subcooled.

{

t L

f QUESTION:

90.

The reactor coolant subcooling margin will be DitacTLY REDUCED by: (Evaluate i

each change separately.)

A.

increased pressurizer pressure.

i l

f B.

increased pressurizer level.

I C.

increased reactor coolant flow.

l D.

increased reactor coolant temperature.

l l

I f

FORM A Page 31 of 35 l

l

PRESSURIEED WATER REAC'ICR CDIERIC FUNDMtENTALS EKAMINATION FORN A QUESTION:

91.

Maximizing the elevation difference between the core thermal center and the steam generator thermal centers and minimiting flow restrictions in the reactor coolant system (RCS) piping are plant desi5ns to:

A.

minimise the reactor coolant systan volume, B.

maximize the reactor coolant system flow rate during forced circulation.

ensure a maximum RCS loop transit time.

L.

ensure RCS natural circulation flow can be established.

QUESTION:

92.

Uith the RCS subcooled and all RCPs stopped, the natural circulation flow rate will NOT be affected by an increare in the:

A.

reactor coolant pressure increase.

B.

time after reactor trip.

C.

steam generator level increase.

D.

steam generator pressure decrease.

f QUESTION:

93.

If departure from nucleate boiling (DNB) is reached in the core, the surface temperature of the fuel clad will:

A.

increase rapidly.

B.

decrease rapidly.

C.

increase gradually.

D.

decrease gradually.

t FORM A Page 32 of 35

t.

e>

PRESSURIEED WATER REAC"ICR GENERIC PUNDMEENTA1A ERANIMATIOR FORN A QUESTION:

94, i

l If the reactor is operated within core thermal limits, then:

l A.

plant thermal efficiency is optimized.

]

)

8.

fuel cladding integrity is ensured.

4 C.

Pressurized thermal shock will be prevented.

l D.-

Reactor vessel thermal stresses will be minimited.

.j l

l QUESTION: 95.

l Fast neutron irradiation of the reactor vessel results in stresses within the vessel metal, thereby the Nil Ductility Transition l

Tamperature.

[

I A.

increased, increasing l

r B.

increased, decreasing l

C.

decreased, increasing D.

decreased, decreasing i

f QUESTION:

96.

i i

The likelihood of brittle fracture failure of the reactor vessel is REDUCED by:

l 1

A.

increasing vessel age.

B.

reducing vessel pressure.

l l

C.

reducing vessel temperature.

I i

D.

reducing gamma flux exposure.

i l

L l

t i

b PORM A Page 33 of 35

i

.s PRRSSURIEED WATER REACITIR GENERIC FtEID4NENTA1A ERAMINATICII i

PORN A-

)

QUESTION:

97.

pressure atress on the reactor vessel vall ist l

l A.

compressive across the entire wall.

3.

tensile across the entire wall-C.

tensile at the inner wall, compressive at the outer well.

I D.

compressive at the inner all, tensile at the outer wall.

l l

t i

QUESTION:

98.

I The nil. ductility temperature is that temperature:

j t

A.

below which the probability of brittle fracture significantly increases.

B.

shore failure stress becomes greater than the yield stress of the m eal..

j C.

below which the probability of plastic deformation significantly j

increases.

I D.

below which the yield stress of the metal is higher than the critical

}

fracture struss.

l QUESTION:

99.

j t

Pressurised thermal shock could most likely be a concern during:

l t

A.

an uncontrolled cooldown followed by a rapid repressurisation.

i i

S.

an uncontrolled depressurisation followed by a rapid repressurisation.

l i

C.

an uncontrolled cooldown followed by a rapid depressurization.

l D.

an overpressurization from a low temperature, low pressure condition.

l l

i PORM A Page 34 of 35

i.

PRESSL5LIEED MTER REACTOIt GWRIC FUNDMMfTALS ERAMINATICII i

l' PORM A QUESTION:

100.

l i

+

t g

During a severe overcooling transient, a major concern to the operator is:

l L

A.

accelerated airconium hydriding.

i B.

loss of reactor vessel water level, i

C.

loss of reactor coolant pump not positive suction head.

j i

L D.

brittle fracture of the reactor vessel.

i t

t t

i i

I k

.j i

t i

f

-l t

i t

I I

t l

l 1

i b

I i

l 1

I i

I PORN A Page 35 of 35 l.

t

~

t '.

f ANSWER KEY l

./

i PWR GTE (FORM A)

[

f i

1.

C.

26.

A.

51.

D.

76.

B.

l' 2.

D.

27.

D.

52.

C.

77.

D.

3.

A.

28.

D.

53.

B.

78.

D.

4.

D.

M 54.

D.

79.

B.

5.

B.

30.

A.

55.

A.

80.

C.

l 6.

B.

31.

B.

a56==4, 81.

C.

7.

D.

32.

C.

57.

B.

82.

C.

8.

C.

33.

A.

58.

D.

83.

A.

}

9.

C.

34.

C.

59.

B.

84.

D.

+

10.

B.

35.

A.

60.

B.

85.

B.

f 11.

B.

36.

D.

61.

B.

86.

D.

12.

D.

37.

C.

62.

D.

87.

C.

13.

C.

38.

C.

63.

D.

88.

A.

l h

39.

B.

64.

A.

89.

B.

15.

C.

40.

D.

65.

D.

90.

D.

f 16.

D.

41.

B.

66.

D.

91.

D.

17.

D.

42.

B.

67.

B.

92.

A.

18.

C.

43.

A.

60.

C.

93.

A.

19.

B.

44.

B.

69.

B.

94.

B.

20.

B.

45.

A.

70.

D.

95.

A.

l 21.

C.

46.

A.

71.

C.

96.

B.

22.

C.

47.

C.

72.

C.

97.

B.

23.

B.

48.

A.

73.

D.

98.

A.

i 24.

B.

49.

D.

74.

A.

99.

A.

j 25.

D.

50.

A.

75.

D.

100. D.

t i

ion t

Pressurized Water Reactor,eneric Fundamentals Exam n r

administered October 4,1989.

Questions 14, 39 an were deleted.

i e

s'

(

e 9

i i

'f m

-.._..~y,.-_,,_...---_._--,.___-,mm,.

.--_~r.,,_

l

.I.

J*

.l UNITED STATES NUC1 JAR RECULATORY COMMIS$10N l

PRESSURIZED WATER REACTOR GENERIC FUNCAMENTALS EXAMINATION t

Please Print i

Name:

i i

Facility:

l ID Number:

i i

I INSTRUCTIONS TO CANDIDATE j

Use the answer sheet provided.

Each question has equal point value. The j

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 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after the i

examination starts.

l 6

.s SECTION Questions 4 of Total Score

'l THERMODYNAMICS 1

28 i

I COMPONENTS 29 71 I

REACTOR THEORY 72 100 TOTALS 100 t

i I

f All work done on this examination is my own.

I have neither given nor i

i i ',

received aid,

?

f Candidate's Signature i

r I

PORM B 1

1

i RULES AND CUIDELINES FOR TH!' CENERIC FUNDAMENTALS EXAMINATION

{

During the administration of this examination the following rules apply:

(1) Print your name in the blank provided on the cover sheet of the l

examination, j

(2) Fill in the name of the facility you are associated with.

(3) Fill in the ID. Number you were given at registration.

(4) Three handouts are provided for your use during the examination, an Equations and Conversions sheet, instructions for filling out the answer l

sheet, and Steam Table booklets, f

(5) Use only the answer sheet provided.

Credit will only be given for l

answers marked on this sheet. Follow the instructions for filling out j

the answer sheet.

t (6) Scrap paper will be provided for calculations, f

l (7) Any questions about an iten on the examination should be directed to the i

I examiner only.

i (8) cheating on the examination vill result in the automatic forfeiture of this examination.

Cheating could also result in severe penalties.

l (9) Restroom trips are limited. Only ONE examinee may leave the room at a l

time.

In order to avoid the appearance or possibility of cheating, avoid l

all contact with anyone outside of the examination room.

{

(10) After you have completed the examination, please sign the statement on f

the cover sheet indicating that the work is your own and you have not received or been given any assistance in completing the examination.

(11) Please turn in your examination materials answer sheet on top followed by the exas booklet, then omanination aids. steam table booklets, handouts and scrap paper used during the examination.

(12) After turning in your examination materials, leave the examination area, as defined by the examiner.

If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeited.

c,

OEHRIC PERIh411 ETA 1A unAarruaTICII SECTION 3Q04710188 AIID 00If75RSICIl8 BAIIDOEFT SMEET ammftcits Cycle Efficiency = par Mark faut) k

- ae AT p

h ry (in) 4 n Ah SCR 8/(1. K,gg)

=

\\

k UA AT CR3 (1. K,gg)g CR II * "off}2

=

2 SUR = 26.06/r M

1/(1 K,gg)

CR /CR

=

g 0

i 26.06 (1,gg p)

(1 K,gg)0

{

SUR =

M

=

$ ' p)

(1

K,gg)g i

(1. K,gg)#,gg f

8

}

P,10 SDN P

=

f f

P,e(*/')

P Pwr va

=

g P

I 1*/(p * #)

{

e (1/p)+l().p)/A,ggr) e f

a (K,gg.1) A,gg 1*

1 x 10 5 seconds p

=

4 AK,ggA,gg A,gg = 0.1 seconds p

=

i i

00lffERSIC3tB j

1 L

t 2.21 lba f

10 3.7 x 10 dps 1 kg 1 Curie

=

3 6

i 3.41 x 10 STU/hr 2.54 x 10 SW/hr 1 Mw 1 hp

=

i 9/5 'C + 32 l

778 ft lbf

'F 1 STU

=

5/9 (*F. 32)

'C

=

i 1

1 1

1

j m

h"'

FRESSURIEED WATER REACTCIL GENERIC FUNWJtENTAIA EXAMINATICII FORN 3

o' QUESTION:

1.

An atmospheric pressure of 15 psia equals:

A.

30 psig.

)

B.

15 psig.

.\\

1 C.

5 psig.

D.

O psig.

)

QUESTION:

2.

Condensate dopression is defined as:

A.

cooling the condensate below its saturation temperature.

B.

maintaining the condensate at a constant temperature throughout the system.

C..

ensuring that the condensate is below the level of the hotwell pumps.

)

1 D.

cooling the condensate to the point of saturation.

l QUESTION:

3.

l What is the reactor coolant system subcooling for Tave - 400'F and pressuriser l

pressure - 1,000 psia?

l

)

A.

75'T l

t B.

100'T i

C.

125'r i

D.

145'F i

I t

i FORM B Page 1 of 34

PRRSSURIT.ED WATER REACTOR GENERIC FUlmMEENTA1A REAMINATION rann B i

d' QUESTION:

4.

The plant is maintained at 2,000 psia with a pressuriser temperature of 636'F.

l A pressuriser safety relief valve is leaking to a collection tank which is being held at 10 psig. What is the temperature of the fluid downstrean of the i

relief valve?

A.

280'F B.

240'F i

C.

190'F l

D..

170'r i

QUESTION:

5.

7

)

Overall plant efficiency will 35533&E3 if:

)

A.

the steam quality is increased by removing moisture from the steam prior to entering the turbine.

{

B.

the temperature of the feedwater enterink the steam generator is increased.

l i

C.

the amount of condensate depression (subcooling) in the main condenser is decreased.

j D.

the temperature of the steam at the turbine inlet is decreased.

j i

QUESTION:

6.

.j The possibility of a water hammer is MINIMIEED by:

A.

changing valve positions as rapidly as possible.

8.

starting centrifugal pumps with the discharge valve fully open.

C.

starting positive displacement pumps with the discharge valve closed.

D.

venting systems prior to starting centrifugal pumps.

I I

+

FORM B Page 2 of 34

p_-

F j

i PRESStat133D MTER REACTCIL ODIERIC FUNDMEntTA1A ERAMINATION FORN 5 i

j. a QUESTION:

7.

l i

cavitation in an operating p'anp may be caused by:

j A.

lowering the auction temperature.

B.

throttling the pump suction valve.

l C.

throttling the pump discharge valve.

l I

D.

increasing the pwep discharge pressure, j

f J

i f

QUESTION:

8.

I The piping system pressure change caused by suddenly stopping fluid flow is j

referred to es:

.i A.

cavitation.

i B,

shutoff head.

C.

water hammer.

j i

D.

flow head, e

i l

1 QUESTION:

9.

If a flow measuring instrument is ElI density compensated, then indicated mass f

flow rate will be:

e A.

the same as actual mass flow rate with a change in temperature of the fluid.

i B.

greater than actual mass flow rate with a decrease in temperature of the

(

fluid.

C.

less than actual mass flow rate with a decrease in temperature of the

{

fluid.

i D.

less than actual mass flow rate with an increase in tosperature of the

~

L fluid.

j i

I t

FORM B Page 3 of 34 j

l

i PRESSURIEED MATER REACTOR GENELIC FUNDMG3fTAIA ERANIMATION f

PORN B i

1 QUESTION:

10.

j Operating two pumps in parallel instead of operating a single pump i

i vill result in:

l A.

a large increase in system head and the same flow rate, f

S.

the same system head and a small increase in flow rate.

C.

a small increase in systen head and a large increase in flow I

rate, I

D.

a decrease in system head and a large increase in flow rate.

l QUESTION:

11.

I Excessive amounts of antrained gases passing through a single. phase (liquid)

[

heat exchanger is HEREhlB&RLE because:

A.

flow blockage can occur in the heat exchanger, i

B.

the laminar layer will increase in the heat exchanger, i

C.

the heat transfer coefficient will increase in the heat exchanger, D.

the temperature difference across the tubes will decrease through the l

heat exchanger.

r I

f QUESTION:

12.

j t

In a two loop pressurized water reactor, feedwater flow to each steam i

generator is 3.3 x 10 lbs/hr at an enthalpy of 419 BTU /lba. The steam exiting sach steam generator is at 800 psia with 1004 steam quality.

Ignoring j

blowdown and pump heat, what is the core thermal power?

i A.

3,411 NWt B.

2,915 NWt l

^

C.

2,212 NWt D.

1,509 MWt i

i l

l l

FORM B Page 4 of 34

V I

r' i

L' PRES 8UILIEED WATER REACTOR GENERIC FUNDAMENTALS EKAMINATION l

PoRM B QUESTION: 13.

l t

Why does nucleate boiling improve heat transfer in the core?

l l

A.

The formation of steam bubbles at nucleation sites on the fuel clad l

allows more heat to be transferred by conduction.

l B.

Heat is renioved from the fuel rod as both sensible heat and latent heat of vaporization, and the notion of the steam bubbles cause rapid mixing l

of the coolant.

t C.

Heat is removed from the fuel rod as both sensible heat and latent heat of condensation, and the heat is transferred directly to the coolant by l

radiative heat transfer.

D.

The formation of steam bubbles at nucleation sites on the fuel clad reduces coolant flow in that area and allows more heat to be transferred by convection, i

QUESTION:

14 Subcooled nucleate boiling is occurring along a heated surface. The heat flux is then increased slightly. What will be the effect on the delta.T between f

the surface and the fluid?

}

A.

Large increase in delta +T because of steam blanketing l

B.

large increase in delta T causing radiative heat transfer to become j

significant i

C.

Small increase in delta T because of steam blanketing l

D.

Small increase in delta T as vapor bubbles form and collapse QUESTION:

15.

What parameter change would save the plant farther away from the critical heat j

flux

i A.

Decrease pressuriter pressure B.

Decrease reactor coolant flow j

C.

Decrease reactor power D.

Increase reactor coolant temperature 1

l l

1 1

PORM B Page 5 of 34 l

' TRESSURIEED WATER MAC1tIR GENERIC FLEEDMEENTAIA EEAMINATICII PORN 8 f.

QUESTION:

16.

l o

I

(,

Tilm boiling is:

A.

heat transfer through e, vapor blanket that covers the fuel cladding, f

V S.

heat transfer being accomplished with no phase change.

I i

C.

the most efficient method of boiling heat transfer.

l l

D.

heat transfer through an oxide film on the cladding.

l i

l-i r

l QUESTION:

17.

j The departure from nucleate boiling ratio (DNAR) is defined as:

l

.i A,

the actual heat flux divided by the critical heat flux at any point along l

a fuel rod.

l S.

the critical heat flux divided by the actual heat flux at any point along a fuel rod.

C, the core thermal power divided by the total reactor coolant mass flow

-l i

rate, D,

the number of coolant channels that have reached DNB divided by the number of coolant channels that are subcooled.

?

)

I QUESTION:

18.

i The reactor coolant subcooling margin will be p1RECTLY REBUCED by: (Evaluate each change separately.)

A.

increased pressurizer pressure.

B.

increased pressurizer level.

C.

increased reactor coolant flow.

{

D.

increased reactor coolant ter;perature, i

1.

I t

I.

i FORM B Page 6 of 34 l

l b

h PRES $1RIEED WATER REAC1tlR GENERIC FUNDAMENTALS IIAN1 NATION

[

PORN B f

QUESTION:

19.

Maximizing the elevation difference between the core thermal conter and the

[

steam generator thermal centers and minimizing flow restrictions in the reactor coolant system (RCS) piping are plant designs to:

l A.

minimize the reactor coolant system volume.

B.

maximize the reactor coolant system flow rate during forced circulation.

i C.

ensure a maximum RCS loop transit time.

}

D.

ensure RCS natural circulation flow can be established.

l

[

QUESTION:

20.

r With the RCS subcooled and all RCPs stopped, the natural circulation flow rate vill glI be affected by an increase in the:

A.

reactor coolant pressure increase.

B.

time after reactor trip.

i C.

steam generator Irvel increase.

D.

steam generator pressure decrease.

l i

QUESTION:

21.

If departure from nucleate boiling (DNB) is reached in the core, the surface l

temperature of the fuel clad will:

A.

increase rapidly.

j B.

decrease rapidly.

C.

increase gradually.

t D.

decrease gradually, I

1

't t

i

(

1 l

FORM B Page 7 of 34 l

I i

PRESSINt1EED WATER REACICR OBERIC PUNDMtINTALO ERAN1mATION o

FORN B

{

QUESTION:

22.

i If the reactor is operated within core thermal limits, then l

L A.

plant thermal efficiency is optimised.

i r

B.

fuel cladding integrity is ensured.

l i

I j'

C.

pressurised thermal shock will be prevented.

[

L D.

reactor vessel thermal stresses will be sinimised.

i r

QUESTION:

23.

I Fast neutron irradiation of the reactor vessel results in stresses l

within the vessel metal, thereby the Nil Ductility Transition l

Temperature, j

1 A..

increased, increasing r

i B.

increased, decreasing j

C.

decreased, increasing D.

decreased, decreasing i

l i

6 QUESTION:

24.

j The likelihood of brittle fracture failure of the reactor vessel is REDEGED j

by*

I i

A.

increasing vessel age.

i B.

reducing vessel pressure, t

C.

reducing vessel temperature.

i D.

reducing gamma flux exposure.

I i

i t

t i

PORM B Page 8 of 34 m

.c.

r-,.y- -, _ _.

,.-.-.r.,_,.,

my_,

_.m,

q FRE88URIED MTER REACTOR OEllERIC FUNDMWfTALS REAMINATION

~'

L FORN B I

l QUESTION: 25.

Pressure stresa on.the reactor vessel wall is:

t A.

compressive across the entire wall.

B.

tensile across the entire wall.

l 1

C.

tensite at the inner wall, compressive at the outer wall.

j D,

compressive at the inner all, tensile at the outer wall.

i i

QUESTION: 26.

e f

the nil. ductility tosperature is that tosperature:

i A.

below which the probability of brittle fracture significantly increases.

l r

B.

where failure stress becomes greater than the yield stress of the metal, j

i C.

below which the probability of plastic deformation significantly l

i increases, i.

D.

below whfch the yield stress of the metal is higher than the critical fracture stress.

{

QUESTION: 27.

l t

t l

Pressurized thermal shock could most likely be a concern during:

j A.

an uncontrelled cooldown followed by a rapid repressurisation.

l B.

an uncontrolled depressurisation followed by a rapid repressurization, f'

1 C.

an uncontrolled cooldown followed by a rapid depressurisation.

I l.

D.

an overpressurization from a low t.mperature, low. pressure condition.

f

]

i

]

QUESTION:

28.

During a severe overcooling transient, a major concern to the operator is:

t A.

accelerated sitconium hydriding.

l B.

loss of reactor vessel water level.

l C.

loss of reactor coolant pump not positive suction head.

D.

brittle fracture of the reactor vessel.

+

FORM B Page 9 of 34 6

I

.. ~ -. - _ -, - _ _ -. -.... _..., - -. _ _. _ _ _. ~ _ _.

FRESS1RIEED WATER RAACTOR OWint!C FUlmMGNTA1A ERAMINATICII FORN 5 QUESTION: 29.

b primary purpose of a pressure relief valve is to:

A.

maintain systen flow, t

B.

maintain system pressure.

C.

maintain system integrity.

D.

maintain system temperature.

J 1

QUESTION:

30.

h n a discharge valve is opened to atmosphere, the pressure on the upstream j

side of ths valve will:

A.

remain the same, and the pressure on the downstream side will incre ue, i

.B.

increase, and the pressure on the downstream side will remain the same.

l I

C.

remain the same, and the pressure on the downstrean side will decrease.

D.

decrease, and the pressure on the downstream side will remain the same.

l I

t QUESTION:

31.

The function of a valve backseat is to.

A.

isolate systen pressure from the packing and stuffing box to minimize l

packing leakage, j

r I

l B.

isolate system pressure from the packing and stuffing box for the purpose

}

of valve repacking.

t

?

c.

provide a backup means of flow isolation in the event of primary seat leakage.

D.

Provide a backup means of flow isolation in the event of a pipe break.

l l

i l

I 1

I i

t l

l l

l FORM B Page 10 of 34 l

a

- -.-..J

l I J' FRESSURIEED WATR REACTOR CMDtIC FUNDMEDf7ALS EXAMINATION FOM B QUESTION '.

32.

After manually positioning a motor operated valve, how is the valve actuator re engaged?

A.

Actuation of the torque switch B.

Manually pulling up on the manual declutch lever

[

i C.

Actuation of either the full.open or full clesed limit switch j

t D.

Actuation of the valve actuator motor in either the open or close direction 1

QUESTION:

33.

i To verify the position of a closed manual valve, the operator should operate l

the valve:

A.

to the fully open position, then reclose it using normal force.

{

i B.

in the closed direction using normal force.

l t

i C.

in the open direction until flow sounds are heard, then close the valve using manual force, i

i D.

in the closed direction until it stops, then close it an additional l

one half turn using normal force.

l QUESTION:

34 Density compensation is used in flow instruments to changa to t'

A.

mass flow rate, volumetric flow rate 8.

volumetric flow rate, mass flow rate C.

fluid pressure, volumetric flow rate D.

differential pressure, mass flow rate l

t FORM B Page 11 of 34 I

1; PRESSLELIEED WATER REACTOR CINERIC FUNDMEENTA1J IIANIMAY10N FORM S j

i QUESTION:

35.

)

If the liquid flowing through a liquid flow rate sensor contains entrained i

voids (gas or stems), indicated flow rate will be l

A.

erroneously high.

i B.

erroneously low.

l C.

unaffected.

i D.

fluctuating.

QUESTION:

36.

l If the equalizing line on a differential pressure (D/P) flow detector is opened, the flow detector indication will' l

A, increase slightly.

)

i B.

decrease slightly.

1 C.

30 to zero.

D.

not change.

QUESTION:

37.

I Flow detectors (such as an orifice, flow nozzle, and venturi tube) measure flow rate using the principle that flow rate is:

A.

DIRECTLY proportional to the differential pressura.

I l

B.

INVERSELY proportional to the differential pressure.

C.

DIRECTLY proportional to the square root of the differential pressure.

D.

INVERSELY proportional to the square root of the differential pressure.

[

l l

FORM B Page 12 of 34

- - + ~

,--,-,-w---,

-,,-<,~-m-s,w..

--w,-

,o

,,,,,m,---o-

..m... -

--m,,,. _,--.., _ -,_..-_ -- --- ---

l FRES8URIEED WATER REACTtNt GENERIC PUNDMlatTALS RIANINATION l

PoRM B 3

i QUESTION:

38, t

The pressure differential between a reference leg and a variable leg is:

f 3

A.

DIRECTLY proportional to the he15ht of the variable leg.

l B.

INVIRSELY proportional to the height of the variable leg.

C.

DIRECTLY proportional to the density of the reference leg.

[

D.

INVEREELY proportional to the temperature of the reference leg.

QUESTION:

39.

If the reference leg of a differential pressure level indicator experiences high ambient temperature, indicated level will:

A.

read less than actual level.

f B.

read greater than actual level, C.

equt.1 the actual level.

[

D.

slowly decrease to zero.

i QUEST 70N: 40.

i The output for a reference les differential pressure level instrument will feil MB[ as a result of:

A.

a break on the reference leg.

I B.

a rupture of the diaphraga in the differential pressure cell.

l C.

the refer,ance leg flashing to steam.

{

I i

D.

a break on the variable leg.

i i

l l

FORM B Page 13 of 34

I FRESSURIEED nlATER REACTOR CENERIC FUNDMEDrTALS EKANIMATION i

PORM B i

QUESTION:

41.

A resistance temperature detector (RTD) operates on the principle that the I

change in electrical resistance of:

i A.

two dissimilar metals is DikECTLY proportional to the temperature change measured at their junction.

i B.

two dissimilar metals is INVEEEELY proportional to the temperature change measured at their junction.

C.

a metal is DIEECTLY proportional to its change in temperature.

D.

a metal is INVERSELY proportional to its change in temperature.

QUESTION:

42.

I l

Two differential pressure level transmitters are installed in a large tank.

If transmitter I is calibrated at 200 degrees F and transmitter II is calibrated at 100 degrees F, then at 150 degrees F:

[

A.

transmitter 1 will read greater than transmitter 11.

t B.

transmitter II will read greater than transmitter I.

C.

transmitter I and II will read the same, i

D.

it is impossible to predict how either transmitter will respond.

QUESTION:

43.

i Scintillation detectors operate on the principle of:

P A.

photodisintegration.

B.

photokinesis.

l l

C.

photomultiplication.

P 1

t D.

photoionization, l

\\

l~

FORM B Page 14 of 34

. ~.

I FatssURIEED WATfR REACTOIL CDERIC FUNDMtENTALS EEANIMATICII

)

ranN QUESTION:

44.

I A Br3 proportional counter detects both neutrons and gammas. Which of the l

following best describes the method used to eliminate th* Samma contribution j

from the detector output?

A.

Two counters are used, one sensitive to neutron and gamma and the other i

sensitive to gamma only. The outputs are electrically opposed to cancel j

the gamma. induced currents and yield a neutron only signal for indication use.

t B.

The BT3 proportional detector records neutron flux of sufficient l

intensity that the gamma signal is insignificant compared to the neutron i

signal and yields a. neutron only signal for indication use.

C.

Camma. induced detector pulses are of insufficient width to generate a significant log. level amplifier output. Neutron pulses are the only on6s with sufficient width to yield a neutron only signal for indication use.

r D.

Neutron. induced current pulses are significantly larger than those from gamma. The detector signal is applied to a circuit which filters out the smaller gamma pulses yielding a neutron only signal for indication use.

QUESTION:

45.

The difference between the setpoint and the measured parameter in an automatic

(

flow controller is called:

A.

gain.

c 1

B.

bias.

5 C.

feedback.

i D.

error.

l QUESTION:

46.

t l

A controller's output is typically insufficient to accurately drive a valve actuator. To overcome this problem, a control loop normally employs:

l A.

a lead / lag unit.

8.

a regulator.

C.

a positioner.

D.

an amplifier unit.

l PORM B Page 15 of 34 l

l l

. ~

FRESSURIEED WATDt REAC1tlR CENERIC FUNDMUDITA1A EKANIMATION i

PORN &

QUESTION:

47.

Why must an operator pay particular attention to auto / manual valve controllers j

left in the manual modef A.

The manual valve control is usually not stable compared to the cutomatic

)

mode.

B.

The valve position will no longer respond to changes in system parameters.

)

1 C.

The controlled parameters will no longer be controlled by the valve position.

D.

The valve can only be operated locally during this time.

QUESTION: 48.

What precautions must be observed when transferring a valve controller from the automatic mode to manual mode of controlf r

A.

Ensure that the proper offset is established between the automatic mode and manual mode.

B.

Ensure that the valve controller output signals are matched between automatic mode and manual mode, C.

Ensure that the valve controller stabilizes in the automatic i

mode before completely transferring to the manual mode of control.

D.

Ensure that the automatic valve controller signal is increasing before transferring to manual mode of control.

j i

QUESTION:

49.

l An indication of centrifugal pump cavitation is:

A.

pump motor amps pegged hip,h.

B.

pop discharge pressure indicating zero, l

C.

pump motor amps oscillating.

l D.

pump discharge pressure indicating shutoff head.

I FORM B Page 16 of 34 I

1

-l

.c PRESSURIEED WATER REACTOR GENERIC PUlfDMEINTALS EIANINATICII PORM S a

I QUESTION:

50.

The term ' shutoff head" for a centrifugal pump indicates that it is pumping

)

at:

i A.

maximum capacity and minimum diEcharge head.

B.

' maximum capacity and maximum discharge head.

/

C.

minimum capacity and maximum discharge head.

l l

l D.

minimum capacity and minimum discharge head.

l 5

i QUESTION:

$1.

i Operating a motor driven cer;triftigal pump for extended periods of time with no -

i flow through the pump will cause:

l A.

pump failure from overspeed.

-}

j B.

pump failure from overheating, i

C.

motor failure from overspeed.

j t

D.

motor failure from overheatin5 l.

l QUESTION:

52.

I ElRJfT1100 the discharge valve on an operating centrifugal pump will cause the MDfM AREPS to and the pump DISCHARGE PRESSIRE to I

A.

increase, increase 7

j 1

f B.

decrease, increase

- p

(.

C.

increase, decrease t'

l t

D.

decrease, decrease l

1 i

i i

f 1

r PORM B Page 17 of 34

- ~ ~.

T

^

)

0.;

FRESSURIZED WATER REAC!OR GDIERIC FUNDMGMTALS EIANIMATION -

PORN B

~ QUESTION:

53.

If the speed of a positive displacement pump is increased, the available not positive suction head (NPSH) will and the probability of cavitation will

'A.

increase, increase

')

B.

decrease, decrease C.

increase, decrease D,

decrease,' increase QUESTION:

54.

Reactor coolant pump motor' amps will if the rotor is 10GEgg and the motor speed will if the rotor EHE&RE.

o-A.

increase, increase B.

increase, decrease C.

decrease, increase l

D.

decrease, decrease QUESTION:

55.

If the generator bearings on a motor generator overheat then:

b A..

the generetor voltage will increase, B.

the generator windings will overheat.

l l

C.

the motor current will decrease.

i D,

the motor windings will overheat.

\\

1 l

t i

1 FORM B Page 18 of 34

FRRSSURIZED WATER REACITIR GENERIC FUNDAMENTA!A EKANIMATION FORN 5.

.l l

r

',W QUESTION:

56.

t

.If the speed of a variable speed centrifugal pump is increased to cause pump

.t flow rate to double, pump motor. current will:

i i

L

'A.

remain constant.

E s

B.

increase two fold (double).

[

'C.

increase four fold.

D.

increase ei ht fold, S

i t

)

QUESTION:

57.

The starting current-in an A;C. motor is significantly h1 her than the 5

p full-load running current because:

A.

starting torque is lower than running torque.

B.

starting torque is higher than running torque, C.

rotor current during start is higher than running current.

j I

D.

rotor current during start is lower than running curr6 t.

h v

?

~l I

QUESTION:

58.

The number of starts for an electric motor in a given period of time should be limited because:

C A.

overheating of the windings can occur.

[

B.

excesrive torque is generated during motor start.

C.

running current is such higher than starting current.

r D.

motors are normally started under full load conditions.

FORM B Page 19 of 34

i PRESSURIEED CATER REACTOR CENERIC FUNDMENTALS EIANINATION FORM B

-s 4

. QUESTION:' 59.

Severe stress in a mechanical component, induced by a sudden, unequally.

distributed temperature reduction is a description of:

t A..

heat stress.

B.

thermal shock.

C.

thermal strain.

D.

heat strain.

is i

l

' QUESTION:

60.

Tube fouling in a heat exchanger.causes heat transfer to decrease by:

p A.

reducing fluid velocity on the shell side of the exchanger.

B.

increasing flow rate through the tube side of the exchanger.

l

\\.

C.

reducing the overall (total) heat transfer coefficient.

D.-

increasing the overall (total) heat transfer coefficient.

i l

l QUESTION:

61.

L Borated water is flowing through the tubes of a heat exchanger being cooled by l

fresh water..The shell side pressure is less than tube side pressure. What l.

will occur as a result of a tube failure?

A.

Depletion of borated water inventory.

B.

Depletion of cooling water inventory.

l l

L C.

Dilution of the borated water system.

D.

Shell pressure will decrease.

FORM B Page 20 of 34

PRESSURIZED WATER REAC'It3R GENERIC PUNDMENTAIA EIANIMATION FORM B QUESTION:

62.

.t What is the reason for bypassing a demineralizer due to high temperature?

i A.

Resins expand and restrict flow through the domineralizer.

B.

The domineralizer decontamination factor is dramatically increased.

C.

Organic compounds used as resins will decompose.

D.

The creation of preferential flowpath through the domineralizer will occur.

' QUESTION:

63.

In the event of a system crud burst, what adverse effect does the crud burst 3

have on domineralizer operation?

i A.

Increases pressure drop across domineralizer B.

Increases flow rate through domineralizer C.

Increases domineralizer outlet conductivity D.

Increases domineralizer inlet pH I

l QUESTION:

64.

Boron concentration in the reacror (primary) coolant system has been de-creasing steadily at approximately 10 ppm per hour while using the deborating domineralizer. After several hours, the rate decreases to 2 ppa per hour.

What is a possible cause for the change in deboration rate?

A.

Temperature of the coolant passing through the domineralizer has decreased.

B.

pH of the coolant has increased significantly.

Flow through the deborating resins has increased sharply.

C.

D.

Deborating resins have become boron saturated.

FORM B Page 21 of 34

y t n, i:

PRESSURIZED WATER REAC'tVR GENERIC FtRMGlNTAIA EIANINATION l

NI

~.-

QUESTION:

65.

j To de energire a component and its associated control and indication circuits, the component circuit breaker should be:-

A.

racked in and tagged.in open position.

+

B.

racked in and tagged in closed position.

C.

racked out and tagged in racked out position.

D.

in:the test position and tagged in test.

.i QUESTION:

6 6 ',

To' ensure reliable local breaker indication is being provided the must be reset after bretker operation.

]

A.

OPEN/C1hSED mechanical flag B.

0 PEN /CIASED indicating lights i

C.

Overcurrent trip flag D.

Spring CHARGE / DISCHARGE flag L

i QUESTION:

67.

l i

A circuit breaker thermal overload device:

A.

compares actual current to a fixed overcurrent setpoint that is equated to temperature and' actuates a trip relay.

B.

when subjected to hiah current, overheats and actuates a circuit-l' l

interrupting device.

C.

senses operating equipment temperature and trips protective circuits at 4

preset limits.

D.

is an induction coil that produces a secondary current proportional to l:

the primary current.

L FORM B Page 22 of 34

f ii I

PRESSURIEED WATER REACTOR CENERIC PUNDAMENTALS EKANINAT&ON FORM B h.

QUESTION: -68.

ip '

t

,t Loss of circuit breaker control power will cause:

A.

breaker line voltage to be zero regardless of actual breaker position.

B.

the rennte breaker position to indicate closed rega:dless of actual breaker position.

C.

inability to operate the brecker locally and remotely.

j

'D.

failure of the close spring to charge following local tripping of the breaker.

QUESTION:

69, t

If a de energized bus is not unloaded prior to closing the output breaker of a three phase generator onto the bus, then:

A.

.an overvoltage condition will occur on the bus.

B.

an overcurrent condition will occur on the generator.

C.

an overvoltage condition will occur between generator phases.

D.

generator undervoltage relay actuation will occur.

1 QUESTION:

70.

Which of the following statements is correct concerning the use of disconnect switches?

A.

Disconnects should be limited to normal load current interruption.

B.

Disconnects may be used to isolate transformers in an unloaded network.

f.

C.

Disconnects are similar to oil circuit breakers, but are manually operated.

l D.

Disconnects must be closed with caution when under load because of l

possible arcing.

l 1

l l.

FORM B Page 23 of 34 l

PRRSSURIEED WATER REACTtMt CENERIC FUNDAMENTAIA EIAMINATION t

FORN 5 t

QUESTION:

71.

Closing a generator output breaker -with the generator frequency much less than grid frequency will cause the generator to trip on:

A.

reverse power.

B.

overvoltage.

L C.

overcurrent.

D.

overspeed.

QUESTION:

72.

The operator has just pulled control rods and changed the effective multipli-cation factor (Keff) from 0.998 to 1.002.

The reactor is:

A.

prompt critical B.

supercritical C.

exactly critical D.

suberitical L

L FORM B Page 24 of 34

q r'

s

_FRESSURIEED WATER REACTOR EENERIC FUNDAMENTALS EEANIMATION I

. -l FORN B'

+

QUESTION:

73.

q The ratio of the number of neutrons in one generation to the number of.

H neutrons in the previous generation is the:

N A.

effective multiplication factor l

+

B.

fast fission factor

'. C.

neutron non leakage factor..

a,.

D.

neutron reproduction factor l

t t

QUESTION:

74.

Reactivity is defined as the:

P A.

-fractional change in neutron population per generation.

~ B.'

number of neutrons by which neutron population changes per generation.

C.

rate of change of reactor power in neutrons per second.

D.'

change in the number of neutrons per second that causes a fission event.

[

QUESTION:

75.

A given amount of positive reactivity is added to a critical reactor in the source (startup) range. The amount added is less than the average effective delayed neutron fraction. Which of the following will have a significant effect on the magnitude of the stable startup rate achieved for this addition?

A.

Prompt neutron lifetime

't B.

Fuel temperature coefficient C.

Average effective decay constant i

D.

Moderator temperature coefficient T

PORM B Page 25 of 34

,....... ~ _ _

7

.i PRESSURIEED WATER REACTOR CENERIC FLNDAMENTA1A EIANIMATION FORM B -

j A

'1

' QUESTION:

76.

~)

Over core life the production of plutonium isotopes with delayed neutron fractions

,,than uranium delayed neutron fractions will cause L..

reactor power.transienta to be near the end of core' life, A.

less, faster.'

L. -

B.

less; slower C.

greater, faster D.

greater, slower-l f

QUESTION:

77.

I An installed neutron source:

A.

maintains the production of neutrons high enough to allow the reactor to achieve criticality.

B.

provides a means to allow reactivity changes to occur in a subcritical t.

reactor.

.C.

generates a. sufficient neutron population to start the. fission process and initiate subcritical multiplication.

D.

provides a neutron level that is detectable on the source range nuclear instrumentation.

L l

QUESTION:

78.

1 l

Why does increasing reector coolant boron concentration cause the moderator temperature coefficient to become less negative?

A.

Reactor coolant temperature increases result in a larger increase in the l

thermal utilization factor.

l' I

B.

Reactor coolant temperature increases result in an increase in the

)

resonance escape probability.

L C.

Reactor coolant temperature increases result in an increase in the total l

non leakage probability.

t D.

The change in resonance escape probability dominates the change in the thermal utilization factor.

y l

l FORM B Page 26 of 34 l'

L 1

(

FRESSURIZED WATF". kEACTOR CENERIC RINDAMENTA1A EIAXINATION-PORM B QUESTION:

79.

Why does the fuel' temperature (Doppler) coefficient becomes less negative at higher fuel temperatures?

A.

As reactor power increases, the rate of increase in the fuel ten?arature diminishes.

3.

Neutrons penetrate deeper into the fuel, resulting in an increase in the fast fission factor.

C.

The amount of self shielding increases, resulting in less neutron absorption by the inner fuel.

D.

The amount of Doppler broadening per degree change in fuel temperature diminishes.

~

i l-QUESTION:

80.

A reactivity coefficient measures change while a reactivity defect (deficit) measures a-change in reactivity due to a change in the measured parameter.

L l

A.

an integrated, total I

l B.

a. rate of, differential C.

a differential, total l

D.

a total, differential QUES'f10N:

81.

J l

During power operation, while changing power level, core reactivity is I

affected most quickly by:

1' A.

boron concentration adjustments, i

B.

power defect (deficit).

C.

xenon transients.

D.

fuel depletion.

FORM B Page 27 of 34

L h

PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EIANINATION FORM B l

. QUESTION:

82.

As moderator temperature increases, the magnitude of differential rod (CEA) worth increases because:

A.

decreased moderator density causes more neutron leakage out of the core.

i.

F B.

moderator temperature coefficient decreases, causing decreased competition.

C.

fuel temperature increases, decreasing neutron absorption in fuel.

D.

decreased moderator density increases neutron migration length, s

QUESTION:

83.

Control rod (CEA) bank overlap:

A.

provides a more uniform differential rod (CEA) worth and axial flux distribution.

B.

provides a more uniform differential rod (CEA) worth and allows dampening of Xenon induced flux oscillations.

C.

ensures that all rods (CEAs) remain within the allowable tolerance j

between their individual position indicators and their group counters and i

ensures rod (CEA) insertion limits are not exceeded.

l D.

ensures that all rods (CEAs) remain within their allowable tolerance between individual position indicators and their group counters and provides a more uniform axial flux distribution.

i QUESTION:

84.

j l

The basis for the maximum power density (kw/ft) power limit is tot j

i A.

prevent fuel clad melt.

l B.

prevent fuel pellet melt.

C.

limit bulk coolant temperature.

D.

prevent nucleate boiling.

i i

FORM B Page 28 of 34

7-n PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EKANINATION FORM B QUESTION:

85.

The control red insertion limits are power level dependent because the magnitude of*

t

'A.

control rod worth decreases as power increases.

B.

power defect increases as power increases.

C.

Doppler (fuel temperature) coefficient decreases as power increases.

D.

moderator temperature coefficient increases as power increases.

QUESTION:

86, p

Fission products that have substantial neutron capture cross sections are:

A.

excited fission products.

I B.

fission product daughter.

+

I C.

radioactive fission products.

D.

fission product poisons.

1 QUESTION:

87.

Following a reactor trip from sustained high power operation, Xenon-135 concentration in the reactor will:

A.

decrease because Xenon is produced directly from fission.

B.

increase due to the decay of Iodine already in the core.

C.

remain the same because the decay of Iodine and Xenon balance each other out.

D.

decrease immediately, then slowly increase due to the differences in the half-lives of Iodine and Xenon.

L FORM B Page 29 of 34

.. - ~

o

' FRESSURIEED WATER REACTOR GENERIC FUNDAMENTAIA EEAKIN6T10N I

FORM B -

-i l

' QUESTION:' 88.

t i

.-(\\ ;

(..

.Following a reactor trip ftom sustained high power operation, the major Xenon t

135. removal process is:

' A.-

ion exchange.

I lB.

beta' decay.

C.,

neutron capture.

?

D.

alpha decay.

QUESTION

89.

~

.r A reactor has been operating at 50 percent pover for 7 days when power is ramped to 100 percent over a four hour period. The new equilibrium Xenon i:

value will:

1 I

'A.

be twice the 50 percent value.

{

B.

be less than twice the 50 percent value.

C.

be more than twice the 50 percent value.

l D.

remain the same since it is independent of power.

i 4

1 Ly I,

QUESTI0ll:

90.

1 Slow changes in axial power distribution in a reactor that has operated at a steady state power for a long time can be' caused by:

1 A..

Xenon peaking.

B.

Xenon override.

l:

C.

Xenon burnup.

D.

Xenon oscillation.

l:

t s

FORM B Page 30 of 34

-. v.

m-.

-1..

e v v FRESSURIEED WATER RRACTOR CENERIC FUNDAIGNTALS EIANIMATION 3

FURN B>

7

. QUESTION:

91.

A reactor that has been operating at rated power for about.two weeks reduces power to 50 percent..Xe 135 will reach a row equilibrium condition in hours.

l A.

8 to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months B.

20 to 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months C.

130'to 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months D.

40 to 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months

' QUESTION:

92.

L L

The reactor is near the end of its operating cycle. In order to stay critical, power and temperature have been allowed to "coastdown." Why is l'

boron no. longer used to compensate for fuel depletion?

' A.

Boron concentration approaches zero and requires excessive amounts of water to dilute.

B.

The differential boron worth has decreased below its useable point.

C.

The boron in the coolant has been depleted due to neutron absorption.

l' D..

"Coastdown" is preferred due to fuel conditioning limitations.

l:

QUESTION:

93.

While withdrawing control rods during an approach to criticality, the count j.

L rate doubles.

What will occur if the same amount of reactivity that caused l

the first' doubling is added again?

A.

Count rate will increase slightly.

'l l

B.

Count rate will double.

.l l

\\':-

C.

The reactor will remain suberitical.

1 3.

The reactor will be critical or slightly supercritical.

i FORM B Page 31 of 34

n.

tL

'*3 FRESSURIEED WATER REACTOR GENERIC FUNDAMENTAIA EEANIMATION

~/'

FORN B c

QUESTION:

94.,

In a reactor with a source,.a non changing neutron flux over a few minutes is indicative of criticality or:

A.-

the point of adding heat.

B.

supercriticality.-

C.

'suberiticality.

D.

equilibrium subcritical count rate.

QUESTION:

95.-

At EOL,-critical-rod (CEA) position has been calculated for a reactor startup j

four hours after a trip from 100 percent power equilibrium conditions. The actual critical rod (CEA) position will be LOWER than the predicted critical

(

rod (CEA) position if:

J A.-

the startup is delayed until eight hours after the trip, j

B.

the steam dump pressure setpoint is lowered by 100 psi prior to reactor startup.

C.

actual boron concentration is 10 'pm acre than the assumed boron p

concentration.

D, one control rod (CEA) remains fully inserted during the approach to J

riticality.

l t

I'

[

QUESTION:

96, 1..

With keff - 0.985, how much reactivity must be added to make the reactor critical?

A.

1,480 pcm (1.48% delta k/k)

B.

1,500 pcm (1.50% delta k/k)

L, C.

1,520 pcm (1.52% delta-k/k)

[

D.

1,540 pcm (1.54% delta k/k) l, l'

FORM B Page 32 of 34

re-f

' c..~

. PREL? RIZED WATER REACTOR CENERIC FUNDAMENTAIA EIANINATION FORM B

-QUESTION:

97.

i t

1

)

If, during a reactor startup, the startup rate is constant and positive

.without any further reactivity addition, then the reactor is:

?

A.

critical.

B.

supercritical.

C.

subcritical..

l D..

prompt critical.

1 3

i QUESTION:

98.

4i.

Civen a critical reactor operating below the point of adding heat, what reactivity effecer are associated with reaching the point of adding heat?

A.

There are no reactivity effects since the reactor is critical.

i

?

5.

The increase,in fuel temperature will begin to create a positive reactivity effect, t

i C.

The decrease in fuel temperature will begin to create a negative reactivity effect.

D.'

The increase in fuel temperature will begin to create a negative reactivity effect.

t QUESTION: 99.

E,hortly after a reactor trip, reactor power indicates 0.5 percent where a stable negative SUR is attained. Reactor power will be reduced to 0.05 percent in approximately seconds.

'A.

360 r

B.

270

/.

C.

180 D.

90 FORM B Page 33 of 34

yw w

- t PRESSLRIED WATR REAc10R CENRIC FUNDMGINTA1A EIANINATION L

roux B.

F f

-QUESTION-

100, 1

The major reason boron is used in a reactor is to permit:

l up l

.A.-

a reduction in the shutdown margin, j

B.-

an increase in the amount of control rods (CEAs) installed..

i:

i

,C.

an increase in core life, o

f L

D.-

a reduction in the effect of resonance capture, l

lr.,

4n s

i i

c 1

1.

1 1.

l l-b k

l-l l

i FORM B Page 34 of 34

i i

+

ANSWER KEY PWR GFE (FORM B) 1.

D.

26.

A.

51.

B.

76.

A.

2.

A.

27.

A.

52.

B.

77.

D..

3.<

D.

28.

D.

53.

D.

78.

A.

4.

- B.

29.

C.

54.

A.

79.

D.

5.

D.

30.

D.

55.

D.

80.

C.

6.

D.

31.

A.

56.

D.

81.

B.

82.

D.

7.

B.

32.

D.

8.

C.

. 33.

B.

58.

A.

83.

A.

9.

C.

34.

B.

59.

B.

M 10.

C.

35.

D.

60.

C.

85.

B.

. 11.

A.

36.

C.

61.

A.

86.

D.

'12.

D.

37.

C.

62.

C.

87.

B.

I 13.

B.

38.

B.

63.

A.

88..

B.

l 14.

D.

39.

B.

64.

D.

89.

B.

15.

C.

40.

D.

65.

C.

90.

D.

16.

A.

41.

C.

66.

C.

91.

D.

l 17.

B.

M 67.

B.

92.

A.

18.

D.

43.

C.

68.

D.

93.

D.

19.

D.

44.

D.

69.

B.

94.

D.

20.

A.

45.

D.

70.

B.

95.

B.

21. ' A.

46.

C.

71.

A.

96.

C.

22.

B.

47.

B.

72.

B.

97.

B.

23.

A.

48.

B.

73.

A.

98.

D.

24.

E.

49.

C.

74.

A.

99.

C.

25.

B.

50.

C.

75.

C.

100.

C.

Pressurized Water Reactor Generic Fundamentals Examination administered October 4, 1989. Questions 42, 57 and 84 were t

deleted.

l c

e y

-v-,,.,,v_

.v.-..-----...,,

.-..--,-,,,_..~r..

.--.-----,-.,r

-

ML19327B544

Text

Dear Mr. Amundson:

Enclosures:

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