ML19327C072

Forwards Generic Fundamentals Exam Section of Written Operator Licensing Exam,Including Answer Keys,Grading Results & Individual Answer Sheets for Each Examinee. Results & Answer Sheet Should Be Forwarded to Examinees

ML19327C072
Person / Time
Site:	San Onofre
Issue date:	10/31/1989
From:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Reeder J SOUTHERN CALIFORNIA EDISON CO.
References
NUDOCS 8911150213
Download: ML19327C072 (39)

Text

tf m r

u_g

[,

octoW 31, 1989

'jl p

.- 4

-l F

Docket No. 50-361/362 Southern. California Edison Company M

San Onofre Nuclear Generating Statien P. O. Box 128 San Clemente CA 92672 Attention: John Reeder, Manager Nuclear Training

Dear Mr. Reeder:

OnOctober4,)1989.theNRCadministeredtheGenericFundamentalsExamination Section(GFES of the written operator licensing examination to employees of I>

your facility.

Enclosed with this letter are copies of both forms of the extminution including answer keys, the grading results for your facility and copies of the it.dividual 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%.

i 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 DocumentRoom(PDR). The results for individual examinees art. exempt from disclosure, therefore enclosures (3) and (4) will not be placed in the PDR.

Should you have any quettions concerning this examination, please contact.

c i-Mr. Paul Doyle at (301) a92-1047.

~

i

' ['

Sincerely,

• 3 s'

< l ',.

L.

?

n h

n g g, 5.s b h f %

7

~

y

)* '

'Z Dennis F. Kirsch, Chief

+

y -

ReactorSafetyBranch)

O

Enclosures:

/ i

(

1.

Examination Form "A"'with answers 4

l.

Examination Form "B" with answers 3.

Examination Results Summary for facility i

t.

' Copies o# Candidates individual answer sheets s

if 8911150213891943 p~~cyr PDR ADOCK 05U pbC V

i fA

jy; 8

w,.

k-y-

I e,.

t 2

October 31, 1989 l

f?

i cc w/o enclosures:

RV Reading Files RV Facility T11es P. Doyie J. B. Martin B. H. Faulkenberry

+'

R. F. Zinnerman -

A. E. Chaffee 1

0. F. Kirsch L. F. Miller s MCLPORj (w/encloyures' 1 aM;2),

s e

RV/jk

iYES)REQUr3T COPY J REQUEST Y,1 REQUESTJ0Q]

/ - NO

] YES /

'O LYES / GNO..)

SEND TO RF

' YES / (N0J l

CROSS [A LMIL M

KIRSCH Ib i-10/p/89 10/H 89 10/3//89

/

4 J y'

e l'

b

.e

i f

w Q.

I UNITF.D STATES NUCLEAR REGULATORY COMh1SSION PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION i

Please Print:

Name:

I Facility:

ID Number:

i INSTRUCTIONS TO CANDIDATE

'Use the, answer sheet provided. Each question has equal point value.

The passing grades require at least 80% on this part of the written licensing

,t 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 exanitiation starts.

SECTION Questions

% of Total Score COMPONE!!TS 1

43 REACTOR THEORY 44 72 THERMODYNAMICS 73 100 TOTALS 100 I

All work done on this examination is my own, I have neither given nor received aid.

Candidate's Signature k

?

l MM A f

1 f

e

r=

O I

RULES AND CUIDELINES FOR 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 f

examination, i

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

(3) Fill in the ID.!: umber you were given at registration.

I (4) Three handouts are provided for your use during the examination, an Equations and Conversions sheet, instructions for fillin8 out the answer sheet, and Steam Table booklets.

(5) Use only the answer sheet provided.

Credit will only be given for answers marked on this sheet.

Follow the instructions for filling out i

the answer sheet.

(6) Scrap paper will be provided for calculations.

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

(8) Cheating on the examination will result in the automatic forfeiture of this examination. Cheating could also result in severe penalties.

(9) Restroom trips are limited. Only ONE examinee may l' eave 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.

i (10) After you have completed the examination, please sign the statement on the cover sheet indicating that the work is your own and you have not i

received or been given any assistanco in completing the examination.

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

I l

(12) After turning in your examination materials, leave the examination area, I.

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.

l l

E'

< l.

i;

~

GENRIC FtMhMEETA1A EEANTEAT!W gBCTIM

[.

ElukT! WS AND 001NERSIW S MANDOUT W t

I i

g i

l a e,AT Cycle Efficiency Mat Mark (aut) 4 h rg (in) 4 5 Ah SCR

$/(1 K,gg)

=

4

= UA AT CRg (1. K,gg)g CR2(

eff}2

=

t i

SUR - 26.06/r M

1/(1. K,gg)

CR /CR

=

g 0

26.06 (A,gg p)

(1 K,gg)0 syR -

N (I

p)

(1 K,gg)t

$3(t)

F P,10 SDN (1. X,gg)/K,gg l

P, e */')

I W 5 P

Pwr g

i (1*/p)+[()-p)/A,ggs) 1*/(p

-)

r f

l

- (K,gg. 1)/K,gg 1*

1 x 10 5 seconds p

l AK,gg/K,gg 1,gg = 0.1 seconds *I l

p l-t Y

l CGNERIIMS f

10 1 Cut'io 3.7 x 10 dps 1 kg 2.21 lba 3

0 1 hp 2.54 x 10 8W/hr 1 Mw 3.41 x 10 BTU /hr i

1 BW 778 ft lbf

'F 9/5 'C + 32 i

5/9 ('F. 32) ll C

e o

l l

l

E

'q t

R ESStRIEED WATER RIAC1tt CENERIC FUIE WLENTALS EIANIMATION l

FORN A l

3 L

QUtsTION:

1.

l The primary purpose of a pressure relief valve is 8.o:

A.

maintain system flow, t

t 8.

maintain system pressure.

l C.

maintain system integrity, f

(

D.

maintain system temperature.

l QUESTION:

2.

When a dischargs valve is opened to atmosphere, due pressure on the upstream i

side of the valve will:

A.

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

B.

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

I i

C.

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

i D.

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

L l

QUESTION:

3.

I The function of a valve backseat is to:

A.

isolate system pressure from the packing and stuffing box to minimize packing leakage.

B.

isolate system pressure from the packing and stuffing box for the purpose of va) e rapacking.

C.

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

D.

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

t h

• 1 1

f FORM A Page 1 of 35

r

6 r

1 FRESSIRIZED WATER REACTOR CNIERIC FUNDAMENTALS EXAMINAT1088 I

FORM A QUESTION:

4.

After manually positioning a motor operated valve, how is the valve actuator l

re engaged?

A.

Actuation of the torque switch l

B.

Manually pulling up on the manual declutch lever C.

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

Actuation of the valve actuator motor in either the open or close I

direction QUESTION:

5.

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.

B.

in the closed direction using normal force.

C.

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

D.

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

QUESTION:

6.

Density compensation is used in flow instruments to change to i

A.

mass flow rate, volumetric flow rate B.

volumetric flow rate, anss flow rate C.

fluid pressure, volumetric flow rate D.

differential pressure, mass flow rate i

FORM A Page 2 of 35

V

t

,9:

<o 1 FRESSIRIEED WATER REAC1t* CENERIC FUNDMENTALS ERAN1 NATION

.l

{

FURN A l

c QUESTION:

7,'

p-If the liquid flowing throu5h a liquid i' low rate sensor contains entrained

., voids (gas or steam), indicated flow rate will be:

l A.

erroneously high.

l 5

5.

erroneously low.

i:

C.

unaffected.

D.

fluctuating.

l c[ !

Qt'ESTION:

8.

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

t r

A.

increase slightly.

l B.

decrease slightly.

a C.

So to zero.

?

D.

not change.

t I

QUESTION:

9, i

Flow detectors (such as an orifice, flow nortle, and venturi tube) measure l

flow rate using the principle that flow rate is:

l A.

E RIGTLY proportional to the differential pressure.

[

l.

B.

INVERSELY proportional to the differential pressure, i

(

1 C.

DIRECTLY proportional to the square root of the differential pressure.

t l

D.

INVIRSELY proportional to the square root of the differential pressure, 1

.i L

1

.?

FORM A Page 3 of 35 1

FRESSURIZED WATER REACTOR GENERIC PUNDAMENTAIA EXANIMATION F0ttM A QUESTION:

10.

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

A.

DIRECTLY proportional to the height of the variable leg.

B.

INVERSRLY proportional to the height of the variable Icg.

C.

DIR5ditLY Proportional to the density of the refersuee leg.

D.

INVERSRLY proportional to the temperature of the reference leg.

QUESTION:

11.

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

A.

read less than actual level.

B.

read greater than actual level.

C.

equal the actual levnl.

D.

slowly decrease to zero.

QUESTION:

12.

The level indication for a reference leg differential pressure level instruuont will fail LQW as a result of:

A.

a break on the reference leg.

B.

a rupture of the diaphragm in the differential pressure cell.

1 C.

the reference les flashing to steam.

D.

a break on the variable leg.

FORM A Page 4 of 35

i PRESSURIEED WATER REACNR CENERIC FUNDAMENYAIA EXANINATION FORN A QUESTION: 13.

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

i A.

two dissimilar metals is DIRECTLY proportional to the temperature change

[

t measured ar. their junction.

B.

two dissimilar metals is INVERSELY proportional to the temperature change measured at thef.r junction, i

C.

a metal is DIREGILY proportional to its change in temperature.

D.

a metal is INVEKSELY proportional to its change in tempetature.

QUE3TIO;b 14.

l Two differential pressure level transmitters are installed in a latge 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 11, i

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, t

QUESTION:

15.

Scintillation detectors opera:e on the principle of:

A.

photodisintegration.

B.

photokinesis.

C.

-photomultiplication.

D.

photoionization.

?!

'l FORM A Pago 5 of 35

~

l FRESSURIZED WATER RLSCTOR CEIMRIC FUNDAMENTALS EXAMINATION FORM A i

i L.

QUESTION:

16.

A BF3 pre

• tional counter detects both neutrons and gammas. Which of the followint c describes the method used to eliminate the gamma contribu'. ion from the cetsutor output?

i A.

Two counters are used, one sensitive to n6utron and gamar and the other sensitive to gamma only. The outputs are electrically opposed to cancel the gamma induced currents and yield a neutron only signal for indication l

use.

B.

The BF3 jroportional detector records neutron flux of sufficient intensity that the gamma signal is insignificant compared to the neutron signal and yields a neutron only si,-nal for indication use.

2 C.

Camma induced detector pulses are of insufficient width to generate a i

significant lo8 level amplifier output.

Neutron pulses are the only ones with sufficient width to yield a neutron only signal for indication use, i

D.

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

QUESTION:

17.

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

flow contf;oller is called:

l l

A.

gain.

B.

bias, l

i C.

feedback.

D.'

error.

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

F i

i, L

f

' PRESSURIZED MATER REACTOR GENERIC FUNDAMENTA1J EIANIMATION r

NA QUESTION:

19.

Why must an operator pay particu'.ar attention to auto / manual valve controllers l

1 eft in the manual mode?

i A.

The manuel valve control is usually not stable compared to the autoastic

)

l node.

5.

The valvo position will no longer respond to changes in systes parameters.

C.

The controlled parameters will no longer be controlled by the valve

[

position, j

D.

The valve can only be operated locally during this time.

r QUEST 10N:

20.

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

A.

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

B.

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

C.

Ensure Stat the valve controller stabilizes in the automatic 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.

i t

QUESTION:

21.

t An indication of centrifugal pump cavitation is:

A.

pump motor amps pegged high.

B.

pump discharge pressure indicating zero.

C.

pump motor amps oscillating, r

(

D.

pump dischcrge pressure indicating shutoff head.

r i

l l

i l

l l

l l

l FORM A Page 7 of 35 l

n-l

<s

t I

)

l FRESSLRIZED WATR REAM GERRIC FUIIDABUDITALS EKAMITATIOil '

l-FORit A W.-

l QUESTION:

22.

1 The term shutoff head" for a centrifugal pump indicates that it is pu. spin; at:

i 3,c A.

maximum capacity and minimum discharge head.

)

i B.

maximum capacity and asximum discharge head.

C.

minimum capacity and maximum discharge head.

j i

D.

minimum capacity and r.timum discharr,e head.

l l

J

. I QUESTION:

23.

Operating a motor. driven centrifugal pump for extended periods of time with no flow through the pump will cause:

I A.

pump failure from overspeed.

B.

pump failure from overheating.

2 C.

motor failure from overspeed.

D.

motor failure from overheating.

QUESTION:

24

+

SHUTTING the discharge valve on an operating centrifugal pump will cause the MOTOR AMPS to and the pump DISCHARGE PRESSURE to l

i A.

increase, increase B.

decrease, increase C.

increase, decrease D.

decrease, decrease I

r

• I FDRM A Page 8 of 35

'r, PRESE'JRIEED ilATER REE* TOR GENERIC PUIEDMtErfAIJ EKAMIi4.TICII I'

fg.' t 70RIt A QUEST;0N:

25,-

l If the speed of a positive displacement purp is increased, the wvailable not positive suction head (NPSH) will and the probability of i

cavitation will i

1 A.

increase, increase

[

i B.

decrease, dervoase C.

increase, decrease D.

decrease, increase QUESTION:

26.

Reactor coolant pump motor amps will if the rotor is LDCKED and the motor speed will if the rotor SHEARS.

A.

increase, increase B,

increase, decrease C.

decrease, increase D.

decrease, decrease f

+

QUESTION:

27.

If the generator bearings on a motor generator overheat then:

A.

the generator voltage will increase.

B.

the generator windings vill overneat.

C.

the motor current will decrease.

D.

the motor windings will overheat.

it

'I f

P i

F0tM A Page 9 of 35

r-

~

I 1

hi ;

PRESSURIZ3D WATER REAC' ITER GENERIC FUNDAIGllNTALS EXAMINATION FORN A

)

l I

QUESTION: 28

)

If the speed of a variable speed centrifuga!. pump is increased to cause pump i

I flow rate to double, pump notor current will:

A.

remain constant.

B.

increase two fold (double),

q inersase four fold.

~

D.

increase eight fold.

i I

QUESTION:

29.

The starting current in an A.C. motor is significantly higher than the full load running current because:

A.

starting torque is lower than running torque.

B.

starting torque is higher than running torque.

l C.

rotor current during start is higher than running current.

D..

rotot current during start is lower than running current.

QUESTION:

30.

The number of starts for an electric motor in a given period of time s.hould be

[

limited becausa:

A.

overheating of the windings can occur.

B.

excessive torque is generated during motor start.

C.

running current is much higher than starting current.

D.

motors are norrs11y started under full load conditions.

I.

t t

FORM A Page 10 of 35 t

.--e n.

m -, ~,

rc s

PRESSIELIEED WATER REACTOR GENERIC Pulpt.MDITALS CLAN 14ATI0tt FORN A QUESTIoW:

31.

Severe stress in a mechanical compowent, induced by a sudden, unequally distributed temperature reduction is a description of:

A.

heat stress.

5.

thermal shock.

C.

thermal strain.

D.

heat.1 train.

QUESTION:

32.

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

A.

reducing fluid velocity on the shell side of the exchcnger.

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.

QUESTION:

33.

Borated water is f13 wing through the tubes of a heat exchanger being cooled by fresh water. The Shell side pressure is less than tube side pressure.

What will occur as a result of a tube failure?

A.

Depletion of borated water inventory.

B.

Depletion of cooling water inventory.

C.

Dilation of the borated water system.

D.

Shell pressure will decrease.

FORM A Page 11 of 35

--4

e PRESSURIEED WATER REACTOR CEKERIC PUNDMtENTALS EXAh:1.sfION t

PORN A 34.

QUESTION:

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

A.

Resins expand and restrict flow through the demineralizer, j

B.

The domineralizer decontamination factor is dramatically increased.

C.

Organic compounds used as resins will decompose.

(

l D.

The cisaeion of preferent 'st flowpath through the domineraliter will occur.

I QUESTION:

35.

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

I A.

Increases preseure drop across demineralizer B.

Increases flow rate through demineralizer C.

Increases desineralizer outlet condactivity i

D.

Increases domineraliser inlot pH t

QUESTION:

36.

Boron concentration in the reactor (primary) coolant system has been decreasing steadily at approximately 10 ppm per hour while using the deboratin$ domineralizer. After several hours, the rate decreases to 2 ppm per hour. What is a possible cause for the change in deboration rate?

i A.

Temperature of the coolant passing th' tough the demineralizer has decreased.

B.

pH of the i:oolant has increased significantly.

C.

Flow thrvugh the deborating resins has increased sharply.

1 D.

Deborating resins have become boron satolated.

l 4

1 FORM A Page 12 of 35 l

i e.

. PRESSLRIZED WATER REACTOR GENERIC PVNDAMENTALS BZANINATION i

FORN A i,

l-L QUESTION: 37.

1 p

To de energise a component and its associated control and indication circuits,

)

the component circuit breaker should be:

A.

racked in and ragged 1 A open position, j

1 B.

racked in and tagged in closed position.

i l

l C.

racked out and tagged in racked out position.

(

D.

in the test position'and tagged in test, j

l s

QUESTION:

38.

To ensure reliable local breaker indication is being provided the must be reset after b:eaker operation, f

i A.

OPEN/CLCSED mechanical flag B.

OPEll/ CLOSED indicating lights C.

Overcurrent trip flag D.

Spring CHARGE / DISCHARGE flag

- i QUESTION:

39.

l A circuit breaker thermal overload device:

I A.

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

i i

i 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, D.

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

i

'I t

n I

?

FORM A Page 13 of 35 r.

,.m

a PRESSURIEED WATER EEACTOR CBIERIC PUNDMGNTAIJ EXANINATIOP f

PORN A I

i' l QUESTION:

40.

l Loss of circuit breaker ccntrol power will cause:

A.

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

B.

the rer.ote breaker position to indicate closed regardless of actual breaker position.

{

i C.

inability to operate tha breaker locally and remotely, D.

failure of the close epring to charge following local tripping of the

[

breaker.

t

.?

QUESTION:

41.

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

A.

an overvoltage condition will occur on the bus.

i B.

an overcurrent condition will occur on the generator.

j C.

an overvoltage condition will occur between generacur phases, j

D.

generator undervoltage relay actuation will occur.

~.

QUESTION:

42.

Which of the followit.g statements is correct concerning the use of disconnect switches?

A.

Disconnects should be limited to normal load current interruption.

t B.

Disconnects may be used to isolate transformers 'n an unloaded network.

[

C.

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

D.

Dis:onnects must be closed with caue;on when unoer load because of possible arcing.

i.

FORM A Page 14 of 35

r 3

'l_

PRESStRIZED MATER REAC1TR CENERIC PUNDMEENTAIA EIANIMATION 1

FORN A QUESTION:

43.

l i

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

j l

A.

reverse power.

4 5.

overvoltage, i

I C.

overcurrent.

l D '..

overspeed.

l 4

QUESTION: 44 The operator has just pulled control rods and changed the effective multipli-cation factor (l',gg) from 0.998 to 1.002.

The reactor is.

A.

pro *.pt critical B.

supercritical C.

exactly critica!

D.

subcritical l

i i

l l

mRM A Page 15 of 35

~~~~

+

U PRESSURIEED WATER REACTTE GkNERIC FUNDAMBfTAIA 1:XAMINATION IDEN A

} '

QUESTION:

45.

f

'The ratio of the number of neutrons in one generation to the number of neutrons in the previous genaration is the 1

A.

effectivs multiplication factor j

i B.

fast fission factor i

C.

neutron non leakage factor D

neutron reproduction factor i

QUF.STION:

46, i

Reactivity is defined as the:

A.

fractional change in neutron population per generation.

l B.

number of neutrons by which neutron population changes per generation.

C.

rate of change of reactor power in neutrons per second, i

D, change in the nun 5r. of neutrons per second that causen a fit.sion event.

l P

QUESTION:

47.

A given amount of positive reactivity is added to a critical reactor in the source (startup) range.

• 1e amount added is less than the average effective delayed neutron fraction. Which of the following will have a significant effect on the m*5nitude of the stable startup rate achieved for this addition?

?

A, Prompt nostron lifetime E.

Tuel temperature coefficient C.

Average eftective decay const ant D.

Moderator temperature coefficient t*:

1 l

'i 1

FORM A Page 16 of 35 1

f_.

i 4-W-

l FRESSLRIEED WATER RfACTOR CENERIC FUNDAMENTALS EKAMINATIOtt FORM A l

QUESTION:

48.

s(,

Over core life the production of plutonium isotopes with delayed neutron

~

l' fractions than uranium delayed neutron fractions will cause near the end of core life, i

reactor power transients to be A.

less, faster 5

B.

less, slower C.

greater, faster.

l D.

greater, slower

[

QUESTION:

49.

An installed neutron source:

I A.

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

B.

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

C.

generates a sufficient neutron population to start the fission process l

and initiate suberitical multiplication.

D.

provides a neutron lovel that is detectable on the source range nuclear

-k l-instrumentation.

l

?

i QUESTION:

50.

Why does increasing reactor coolant boron concentration cause the moderator L

temperature coefficient to become less negative?

A.

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

l-thermal utilization factor.

l B.

Reactor coolant temperature increases result in an increase in the i

resonance escape probability, i

iF C.

Reactor coolant tenperature increases result in an increase in the total I

non leakage probability.

t D.

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

l l

NRM A Page 17 of 35 7

L FRRS8URIEED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION

)

FORM A QUESTION:

51.

I Why does the fuel temperature (Doppler) cotificient becomes less negative at I

higher fuel temperatures?

A.

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

1 5.

Neutrons penetrate deeper into the fuel, resulting in an increase in the

)

fast fission factor, j

C.

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

D.

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

QUESTION:

$2.

A reactivity coefficient measures change while a reactivity 1

defect (deficit) mearures a change in reactivity due to a change in the measured parameter.

A.

An integrated, total B.

A rate of, differential C.

A differential, total D.

A total, differential QUESTION:

53.

During powcr 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 l-l

F PRES 5tRIZED WATER REACTOR CENIELIC FUlmAMENTALS EEANINATION POEM A QUESTION:

54 As moderator temperature increases, t':0 magnitude of differential rod (CEA) z worth increases because:

A.

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

B.

moderator temperature coefficient decreases, causing decreased cospetition.

C.

fuel temperature increases, decreasing neutron absorption in fuel.

D.

decreased moderator density increases neutron migration length.

QUESTION:

55.

Control rod (CEA) bank overlap:

A.

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

B.

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

C.

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

i D.

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

provide a more uniform axial flux distribution, i

QUESTION:

56, the basis for the maximum power density (kw/ft) power limit is to:

A.

prevent fuel clad melt.

B.

prevent fuel pellet melt.

C.

limit bulk coolant temperature.

D.

prevent nucleate boiling.

l l

l FORM A Page 19 of 35

F I

PRES 8URIEED WATER RNAC1TIR CENERIC MINDAMENTA1.5 EXAMINATION FORN A QUESTION:

57.

The control rod insertion limits are power level dependent because the t

magnitude of:

A.

control rod worth decreases as power increases.

B.

power defect increases as power increases, C.

Doppler (fuel temperature) coefficient decreases as power increases.

D.

moderator temperature coefficient increases as power increases.

QUESTION:

58.

Fission products that have substantial neutron capture cross sections are:

A.

excited fission products.

B.

fission product daughter.

C.

radioactive fission products.

t D.

fission product poisons.

QUESTION:

59.

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

l A.

decrease because Xenon is produced directly from fission.

l l

B.

increase due to the decay of 20 dine already in the core.

I c.

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

L D.

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

l l

l 1

\\

i l

l L

l FORN A Page 20 of 35

4 IRESSLRIEED nlATER REAC1tR GENERIC PUNDMfENTAIA EEAltIMATICII l

70EN A t

QUESTICII:

60.

Following a reactor trip from sustained high power operation, the major

{

Xenon 135 removal process is.

ol A.

ion exchange.

E.

beta decay.

C.

neutron capture, i

D.

alpha decay.

l t

QUESTION:

61.

l t

A reactor has been operatin6 at 50 percent power for 7 days when power is l

ramped to 100 percent over a four hour period. The new equilibrium Xenon i

value will:

j A.

be twice the 50 percent value.

B.

be less than twice the 50 percent valun.

i C.

be more than twice the 50 percent value.

D.

remain the same since it is independent of power.

QUESTION:

62.

r Slow changes in axial power distribution in a reactor that has operated at a i'

steady state power for a long time can be caused by' 4

A.

Xenon peaking, f

B,(

Xenon override.

l C.

Xenon burnup.

I D.

Xenon oscillation.

?

I ll i

IURM A Page 21 of 35 l

7 Y

i PRESSTRIEED WATER REACITE CENERIC FUNDANENTALS EKANIMATION FORN A l

L QUESTION:

63.

1 t

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

___ hours, j

A.

8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />

)

3.

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

30 to 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> D.

40 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> f

QUESTION:

64.

The reactor is near the end of its operating cyc.le.

In order to stay critical, power and temperature have been allowed to 'coastdown." Why is boron no longer used to compensate for fuel depletion?

A.

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

l I

B.

The differential boron worth has decreased below its useable point.

C.

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

i D.

"Coastdown" is preferred due to fuel conditioning limitations.

QUESTION:

65.

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

[

rato doubles. What will occur if the same amount of reactivity that caused j

the first doubling is added again?

A.

Count rate will increase slightly.

B.

Count rate will double.

C.

The reactor will remain suberitical.

D.

The reactor will be critical or slightly supercritical.

t l

.1 l

l FT)RM A Page 22 of 35 i

f5 l

l PRESSURIEED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION i

FORM A QUESTION:

66.

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

indicative of criticality or'

)

A.

the point of adding heat.

l 8.

supercriticality.

1 C.

suberiticality.

f D.

equilibrium subcritical count rate.

QUESTION:

67.

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

four hours after a trip from 100 percent power equilibrium conditions.

The actus1 critical rod (CEA) position will be LOWER than the predicted critical l

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

[

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.

L QUESTION:

68.

t With k [f - 0.985, how much reactivity must be added to make the reactor

'f criticI A.

1,480 pcm (1.48% delta k/k) t B.

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

C.

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

D.

1,540 pcm (1.54% delta k/k) l FORM A Page 23 of 35 i

--l E fl

~

~

6 t

,V."

b; +

1. T t

FRESSURIEED W.LTER REACTJR GENERYC FUNDI W.TALS EKANINATION

,,?

PORN A

, n.L '

5 QUESTION: 69.

r Ji..

1 7h If, during a reactor startup, the startup rate is constant and positive t

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

4;'.

A; critical.

B.

supercr*r'a*1.

C.

suberitical.

D.

prompt critical.

i QUFSTION:

70.

Civen a critical reactor operating below the point of adding heat. What l

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.

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

reactivity effect.

'The increase in fuel temperature will begin to create a negative

.)

D.

l reactivity effect.

L l

L

-QUESTION:

71.

Shortly after a reactor trip resctor power indicates 0.5 percent where a stable negative SUR is attained. Reactor power will be reduced to 0.03 percent.in apptoximately seconds.

A.

360 B,

270 C.

180 D.

90

'l' FORM A Page 24 of 35 a

JJ&

,6

g-..,

o.

J

.s

,l

" /f '

'i' PRESSURIEED WATER REnuf0'A CENERIC E11NDAIGDfTALS EIAMINATION L.

/

PtlRN A i

i

' y.;. -

' QUESTION:

72.

i t, -

E

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

W A.'

a reduction in the shutdown margin.

B.

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

1 C.

an' increase in core life.

D.

a reduction in the effect of resonance capture.

i A

i I

s

(

k i

f

s3, 4

n p

4 l'-

FORM A Page 25 of 35 i

i c

a w

e

,a e

---m

y 4.

gs f

.9.

' FRESSURIZED WATER RF).CTOR GENERIC TUNDAMENTAIE EKANINATION q

LeS J:

kORN A

?,,,

S' QUESTION: -73.

.An atmospheric pressure of 15 psia equals:

1

' A '.

30 peig.

i J

B.

15 psig.

C.

5 psig.

l D.

0 psig.

QUESTION:

74.

Condensate depression is defined as:

A.-

cooling the condensate below its saturation temperature.

B.

maintaining the condensate at a constant temperature throughout the system.

1

.C.

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

D.

cooling the condensate to the point of saturation.

QUESTION:

75.

What is the reactor coolant system subcooling for Tave - 400'F and pressurizer pressure - 1,000 psia?

A.

75'F 4

B.

100*F C.

125'F D.

145'F

.t 6

)

v FURM A Page 26 of 35

'l s

i

/h'

-PRESSURIEED WATER REACTOR CDIERIC PUNDAMENTALS EKANINATION

)

V.

FORN A

, n.

QUESTION:

76.

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

A pressurizer safety relief. valve is leaking to a collection tank which is c,.

being held at 10 pois. What is the temperature of the fluid downstream of the relief valve?

A.

280*F B.

240*F C.

190'F i

D.

170*F QUESTION:

17.

Overall plant efficiet.cy will DECREASE if:

A.

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

B.

the temperature of the feedwater entering the stear. generator is

' increased.

i C.

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

D.

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

QUESTION:

78.

The possibility of a water hammer is HIRI51 ZED by:

A.

changing valve positions as rapidly as possible.

B.

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.

E b

FORM A Page 27 of 35

.r.

_.. _., __ _ ~.

y[ _,

s.,

n' i

' PRESSURIZED WATER REACTOR'CENERIC FUNDAMENTALS EXAMINATION J

FORN A I

QUESTION:

79.

b..

, i Cavitation in an operating pump may be caused by:

V

, A'.

Iowering the suction temperature.

.B.-

thro::tling the pump suction valve.

t 3.

-C.

throttling the pump" discharge valve, i

D.

it. creasing the pump discharge pressure, j

QUESTION:

80 l

The' piping system pressure change caused by suddenly stopping fluid flow is referred to as:

p; A.

cavitation, s

B, shutoff head.

C.

water hammer.

D.

flow head.

QUESTION:

81.

If a flow measuring instr.unent is g}f density compensated, then indicated mass flow rate will be:

A the same as actual mass flow race 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 t.he fluid.

D.

'less than actual mass flow rate with an increase la temperature of the fluid.

a 3,

i FORM A Page 28 of 35 t (

., ~ - -

,c.-r.,_,

-n

+

,,e r-

FRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION t

FORN A g.

QUESTION:

82.

Operating two pumps in parallel instead of operating a sine,le pump will result in:

A.

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

\\

B.

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

C.

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

D.

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

QUESTION:

83.

Excessive amounts of entrained gases. passing through a sing 1c phase (liquid) heat exchanger is UNDESIRABLE because:

A.

flow blockage can occur in the heat exchanger.

B.

the' laminar layer will increase in the heat exchanger.

C.

the heat transfer coefficient will increase in the heat exchanger.

D.

the' temperature difference across the tubes will decrease through the

.j heat exchanger, j

l QUESTION:

84.

1 In a two-loop pressurized water reactor, feedwater flow to each steam generator is 3.3 x 10 lbm/hr at c.n enthalpy of 419 BTU /lbm The steam exiting each steam generator is at 800 psia with 100% steam quality.

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

j l

A.

3,411 MWt B.

2,915 MWt C.

2,212 MVt i

D.

1,509 MWt FORM A Page 29 of 35

.n

l o.

?

PRESSURIZED WATER REACTOR CENIRIC PUNDAMENTALS EXAMINATION 4

FORN A QUESTION:

85.

Why does nucleate boiling improve heat transfer in the core?

A.

The formation of steam bubbles at nucleation sites on the fuel clad allows more heat to be transferred by conduction.

B.

Heat is removed from the fuel rod as both sensible heat and latent heat of vaporization, and the motion of the steam bubbles cause rapid mixinb of the coolant, j

C.

Hect is removed from the fuel rod as both sensible heat and latent heat of condensation, and the heat.is transferred directly to the coolant by radiative heat transfer.

D.

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

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

QUESTION:

86.

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

A.

Large increase in delta-T because of steam blanketing Large increase in delta-T causing r'adiative heat transfer to become B.

significant C..

Small increase in delta T because of steam blanketing 9

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

87.

What parameter change would move the plant farther away from the critical heat l

flux?

r A.

Decrease pressurizer pressure B.

Decrease reactor coolant flow C.

Decrease reactor power D.

Increase reactor coolant temperature 3

FORM A Page 30 of 35 3

FnT--

o t'

?

4 C :.

c

'. FRE88URIZED WATER REAC"CR CENERIC PUNDAMENTALS EXAMINATION FORN ' A h*

QUESTION:

88.

. Film boiling is:

A. :

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

l B.

. heat transfer' being accomplished with no phase change, a'

C.-

'the most efficient method of boiling hear, transfer.

D.-

heat transfer through an oxide film on the cladding.

/

'QUESTI0h:

89.

,t 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

-a fuel rod.

B.

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

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

D, the number of coolant channels that' have reached DNB divided by the o,. number of coolant channels that are subcooled.

L QUESTION:

90.

p L

l The reactor coolant subcooling margin will be DIRECTLY.REQUCED by: (Evaluate L

each change separately.)

k E

A.

incretsed pressurizer pressure.

B.

increased pressurizer level.

C.

increased reactor coolant flow.

D.

increased reactor coolant temperature.

1.-

i 5'

I d

El' 1,

l' FORK A Page 31 of 35 j.

I

~

4 a

i PRESSURIZED WATER REACTOR CENERIC FUNDA.E NTALS EKAKINATION FORD A n

-QUESTION:

91.

Maximizing th) elevation difference between the core thermal center and the steam. generator thermal centers and minimi. zing flow restrictions in the reactor coolant system (RCS) piping are plant designs to:

?

A.

minimize the reactor coolant system volume.

B.

maximize the reactor coolant system flow rate during forced circulation.

C.

ensure a maximum RCS loop transit time.

D.

ensure RCS natural circulation flow can be established.

QUESTION:

92.

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

A.

reactor coolant pressure increase.

B.

time after reactor trip.

C.

steam generator level increase.

D.

steam generator pressure decrease.

QUESTION:

93.

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

A.

increase rapidly.

B.

decrease rapf.dly.

C.

increase gradually.

D.

decrease gradually, 4

FORM A Page 32 of 35

fC '

g,,.J)

,y

's;

.g PRESSUKIEED WATER REACTtML CENERIC PUITAMENTALS EEAMINATION 3'

PORM A

.r-1

, QUESTION:. 94.

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

?

A.

plant thermal efficiency is' optimized.

B.

fuel cladding integrity,is ensured.

C.

Pressurized thermal shock will be prevented.

D..

Reactor-vessel thermal stresses will'be minimized.

't QUESTION:,)95.

Fast neutron irradiation of the reactor vessel results in stresses with,in the vessel metal, thereby the Nil-Ductility. Transition j

Temperature, o

A.

. increased,' increasing iB.-

increased, decreasitig C.

decreased,' increasing D.

decreased, decreasing

-1 QUESTION:

96.

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

l i

A.

increasing vessel age.

B.

reducing vessel pressure.

~,'

1

,C..

reducing vessel temperature.

D.

reducing gamma flux exposure.

1 i

d

i

)

s, 8

FORM A PaFe 33 of 35

- a n,:-

3--,

33 (p

4' t

t jy e o

):

PRESSURIEED WATER REACT 0k CElWRIC FUNDAkE;iTALS EIANINATION PORM A i

P.

QUESTION:

97.-

i p,.;

Pressure stress on the. reactor vessel wall is:

f

+

A.

c spressive across the entire sell.

l B.

tensile across the entire wall.-

C.

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

'D.-

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

QUESTION:

98.

1; The nil ductility temperature is that temperr.ture:

(

.~ A.

below which the probability of brittle fractare significantly increases.

B.

where failure stress becomes greater than the yield stress of the metal.

f C.

below which the probability of plastic deformation significantly increases.

'D.-

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

QUESTION:

99.

i Pressurized thermal shock could most likely be a concern during:

(

A.

an uncontrolled ccoldown followed by a rapid repressurization.

,B.

an uncontrolled depressurization followed by a rapid repressurization.

C.-

an uncontrolled cooldown followed by a rapid depressurization.

D.

-an overpressurization from a low temperature, low-pressure condition.

4 9

i FORN A Page 34 of 35 1r y

-te s

v

-e-i--

g-gw,,-

y w

p-p-

y y-y

~-

t--s--,r-evy we

g., -.

Jt:0,b

]

1

^

^ ** < t

. <c a> > '

, PRESSURIZED WATER REACTOR GENERIC FUNDAMENTA13 EXAMINATION i i PORM A

\\

.q, QUESTION:

100...

)

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

~~

A.

accelerated.zirconiu:n hydriding.

'l

~ B.'

loss cf reactor vessel water level.

C.

loss of reactor coolant pump not positive suction head.

D.

brittle -fractute cf the reactor vessel.

b L

t t

I 4

r b

F I

FORM A Page 35 of 35

'k

J'4

' 4>, '

, ;+ U

' UNITED STATES NUCLEAR REGU1ATORY COMMISSION PRESSURIZED WATER REACTOR GENERIC WNDAMENTALS EXAMINATION s,,

Please Print:

Name:

' Fac.ility:

ID Number:

INSTRUCTIJNS TO CMDIDATE Use the answer sheet provided.

Each question has equal point value. The passing grades require at least 80% on'this part of the written licensing

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

d.: p SECTION Questions-t of Total Score THERMODYNAMICS 1.-

28 L.

COMPONENTS 29 - 71

[

REACTOR THEORY 72 - lv0 l

1.

TOTALS 100 1

i L'

1' l,

l

'All work done on this examination is my own.

I have neither given nor l

received aid.

1 1^

1' r'.

Candidate's Signature

}

l l=.c i

r i

NMB 1

I.,

s l'

4 k

O n

~

r

,,w-,,

,rv.

or y_.

,-- -,... ~.___

W

\\

- e, f:

t RULES AND Gl'!DELINES FOR THE CENERIC FUNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:

(1)' Print your nana in the blank provided on the cover ' shout of the examination.

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

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

(4) Three handouts are provided for your use during the examination, an Equations and Conversions sheet, instru:tions for filling out the answer sheet, and Steam Table bookle';s.

(5) Use only the answer sheet provided. Credit will only be given for answers marked on this sheet.

Follow the ins tructions for filling out the answer sheet.

' (6)' Scrap paper will be provided for calculations.

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

(2; Cheating on the exsmination will result in the automatic forfeiture of this examination.

Choating could also result in severe penalties.

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

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

(10) After you have completed the examination, please sign the statement on the cover sheet indicating that the work is your own and you have not received or been given any assistance in completing the examination.

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

m-t GENERIC FWDAIERTALS IIANINATI0tt SECTICII BQUATICIIS AllD 00NVERSIGIls HAllDOUT SHERT j

s l

l)

~

M RI Cycle Efficiency = Het Work (out) a

- ac AT p

Energy (in) 6 a Ah SCR S/(1. K,gg) k UA AT cry (1 - K,gg)g CR2 (1. K,gg);

=

SUR - 26.06/r

1 1/(1. K,gg)

CR /CR y

0

' N.05 (A,gg p)

(1.

K,ff)o 1

SUR =

M

=

(3

.o)

(1. K,gg)g 10 " It}

8 P

P SDM (1. K,gg)/K,gg

=

i P,e(*/')-

W Ia P

Pwr g

(1*/p)+[(3-p)/A,,g]

l*/(p - p)

.r p

r (K,gg - 1)/K,gg 1*

1 x 10 5 seconds p

=

• 1 AK,gg/K,gg A,gg - 0.1 seconds p.-

1 GQtEERHalli 10 1 Lurie 3.7 x 10 dpa 1 kg 2.21 lba 3

6 1 hp 2.54 x 10 BTU /hr 1 Mw 3.41 x 10 BTU /hr 1 BTU 7 78 ft-lbf

'F 9/5 *C + 32

• C 5 ') (*F. 32)

ir<

c s.

d FRESSURIZED' WATER REACTOR CENERIC FUNDAMENTALS EXAKINATION H

,,?-t s FORM 5 d.'s

(

r JQUESTION:- 1.

-An atmospheric pressure of 15 psia equals:

A.

30 psig.-

B.

15 psig.

C.

5 psig.

D.

O psig.

I QUESTION:

2.

Condensatc' depression is dafined as A '.

cooling the condensate below its saturation temperature, B.-

maintaining the condensate at a constant temperature throughout the system.

C.

.ensurius that the condensate is b'elow the level of the hotwell pumps.

D.

coolics the cordensate to the point of aaturation.

l.

. QUEST 1 J:

3.

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

prensure - 1,000 psia?

/

i A.

75'F l.

B.'

100'F

(

C.

125'F L

I

?

D.

145'F l

h 1

t w

IVRM B Page 1 of 34 1.

?

m

,t t

.'r*-

s, l

r PAESSURIZED WATER REACTOR. GENERIC FUNDAMENTA1Ji EIANINATION PokN B e,

U QUESTION:'

4.-

V

.The plant is maintained et 2,000 psia with a pressurizer temperaturn of 636'F.

t A pressurizer safety relief valve is leaking to a collection tank which is ibeing held at 10 psig. What is.the temperature of the fluid downstream of the

~

relief valve's t

A.

280'F 8.

24v'F C.

'190'F-4 D.

170*F:

t t

QUEATION:

5.

i Overall plant efficiency will DECREASE if:

l A.

tha r:: cam. quality ia increased by removing moisture from the steam prior to entering the turbine.

B.

tbs. temperature of the feedwater entering the steam generstor is increased.

C.

the amount of condensate derrascion (subcoolin6} in the main condenser is decreased.

D.

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

l 5

Qt'ESTION:

6.

l The possibility of a water hammar is HIH11HJ;D by:

E A.

changing valve positions as rapidly as possible.

B.

starting centrifugal pumps with the discharge valve fully open.

C.

' starting positive displacement pumps with the discharge valvo closed.

D.

venting systems prior to starting centrifugal pumps.

h 1

j.

L FORM B Page 2 of 34 o

~

E.

a

3. _ ~

O lV Q; o '

FRE860RIEED WATER REACTOR GENERIC FUNDAMENTAIA EIAM74AT10N PORM B

tc

,a h'

QUESTION:

7.

~

~ Cavitation in an operating pump may be caused by:

A.

lowering the suction temperature.

B.

' throttling the pump suction valve.

C.

throttling the pump discharge valvc.

D.

increasing the purp discharge pressure.

QUESTION:

8.

The piping system pressure change caused by suddenly stopping fluid flow is raferrod to as:

A.

cavitacion.

B.

shutoff head, 4

t.

water hammer.

D.

flost head.

.QUSSTION:

9.

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

' flow rate will be:

A.

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

B.

greater than actual' mass flow rate with a decrease in tamperature of t.ha fluid.

s 1

C.

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

fluid, i

D.

less than actual mass flow rate with an increase in temperature of the fluid.

j

!l

.l i

FORM B Page 3 of 34

,.__e, m,

(~

c.

PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION l

FORM B

- QUESTION:

10.'

Operating two pumps in parallel.instead of operating a single' pump will result in:

A.

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

B.

the same system head and a smali in: cease in flow rate.

~

C.

a small foerease.in systew head and a large increase in flow rate.

D.

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

QUESTION:

11.

Excessive amounts of entrained gaces passing through a single-phase (liquid) heat exchsager'is UNDESIRARTM because:

~

A.-

flow blockage can occur in the heat exchanger.

B.

.the laminar layer will increase in the heat exchanger.

C.

the heat transfer coefficient will increase in the heat exchanger.

D.

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

L QUESTION:

12.

In a two loop pressurized water reactor, feedwater flow to each steam generator is 3.3 x 10 lbm/hr at an enthalpy of 419 BTU /lbm. The steam exiting each steam genere or is at 800 psia with 100% steam quality.

Ignoring blowdown and pump heat, what is the core therms 1 power?

i 1.

l A.

3,411 MWt B.

.2,915 MWe l

C.

2,212 MWt D,

1,509 MWt l

1 i

FORM B Page 4 of 34 1

l L

c O h.;

s.-

F??.85URIZED WATER REAC'IOR CENERIC FUNDAMPJfTALS EIANINMION FOR" B QUESTION:

13.

Why does nucleate boiling improve heat transfer in the cora?

A.

The formation of steam bubbles at nucleation siter on the fuel clad allows more heat to be transferred by conduction.

B.

Heat is removed from the fuel rod as both sensible heat and latent heat of vaporization, and the motion of the steam bubbles cause rapid mixing of the coolant.

C.

Heat is removed from the fuel rod as both sensible heat and latent heat of condausation, and the heat is transferred directly to the coolant by radiative heat transfer.

D.

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

QUESTION:

14.

i Subcooled nucleate boiling is occurring along a heated surface.

The heat flux is then increased slightly. What will be the effect on the delta-T between the surface and the fluid?

A.

Large increase in delta T because of steam blanka*ing 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:

15.

a What paremeter change would move the plant farther away from the critical haat l

flux?

A.

Decrease pressurizer pressure B.

Decrease reactor coolant flow

{

C.

Decrease reactor power l

e D.

Increase reactor coolant temperacure l

l FORM B Page 5 of 34 er.

e

.e.-

=m

+

Wi',

.j = jf PRESSURIZED WATER REACTOR GENERIC FUNDAM.9NTALS EKAMINATION FORM B N:..1

. QUESTION:

16.

Film boiling is:

A.

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

i B.'

heat, transfer being accomplished with no phase change.

C.

the most' efficient method of boiling hsat transfer.

D.

heat. transfer through an oxide film on the cladding.

7 QUESTION:

17.

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

C.'

the core thermal' power divided by the total reactor coolant mass flow rate.

D.

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

b QUESTICN:

18.

The reactor coolant subcooling margin will be DIRECTLY REDUCED by: (Evaluate C

each change separately.)

A.

increased pressurizer pressure, f

- B.

increased pressurizer level.

C.

. increased reacter coolant flow, i

D.

increased reactor coolant temperature.

I i

FORM B Page 6 of 34

,l

...,,c r

U-4 FRESSURIEED WATER REACTOR GENERIC FUNDAMENTALS EIANINATION FOR M B' d '

g

' QUESTION:

19.

Maximizing the elevation difference between the core thermal center and the steam generator thermal centers ar.d minimizing flow restrictions in the reactor coolant system,(RCS) piping are plant designs to:

A.'.

minimize the. reactor coolant system volume.

B..

maximize the reactor coolant system flow. ste during forced circulation.

' C.

ensure a maximus RCS loop transit time.

t D.

ensure RCS natural circulation flow can be established.

QUESTION:

20.

. With the RCS subcooled and all RCPs stopped, the natural circulation flow rate will HDI be affected by an increase in the:

A.

reactor coolant pressure increase, B.

time after reactor trip.

C.

steam generator level increase.

D.

steam generator pressure decrease.

QUESTION:

21.

If departure from nucleate boiling (DNB) is reached in the core, the surfaco temperature of the fuel clad will; f,

A.

' increase rapidly.

B.

decrease rapidly.

l C.

increase gradually.

D.

decrease gradually.

1' l:

l l'.

o

\\

/

l

t FORM B Page 7 of 34

,4 I,,

+

,.m.,

,,,,e

,.,._r

'u 6-L-

FRESSURIZED WATER REACTOR GENERIC MINDAMENTA13 EKAMINATION pong 3 4..-

i

. QUESTION:

22.'

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

JA.

plant thermal efficiency is optimized.

B.

. fuel cladding integrity is ensured.

C.

pressurized thermal shock'will be prevented.

1 D.

reactor vessel thermal stresses will be minimized.

t i

QUESTION:- 23. '

L L;

Fast neutron irradiation of the reactor vessel results in stresses within the vessel metal, theruby the Nil-Ductility Transition Temperature.

l A.

increased, increasing B.

increased, decreasing C,

decreased, increasing D.

decreased, decreasing

_ QUESTION:

24.

1he likelihood of brittle fracture failure of the reactor vessel is REDUCED by:

A.

increasing vessel age.

-f B.

reducing vessel pressure.

C.

reducing vessel temperature.

D.

reducing gamma flux exposure.

1 l

1 ll l

[

FORM B Paga S of 3'.

l, e l' i'

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

@M., lef.e y.,

,. R T.. W R %v'~s"m, W-M, g y W., o v m;.

Q

y w.e.

v,4

{ 1.f b,,,

+

i x m..

")

.=g

., s.

..4 s

g I

4 g

,q

. p3 n; ov.e ' >s

.N#

h' 4

i

(

i D

s

{,' '

,.,a.c 3. s',.,.'ys. f,.4,0,: -[',c<y 4

g. "2 j..t.

(-

p#

r y

y.

i t

.e,. 4:k g' s *. ' g, 9,-a ',"

.q

,,..y' a c.

-n, g

3 e

,c 4'

j r

4 ; - 4

-,i

f p.

,y-8 57 l

f.p\\

,t 2.

f.. p.

.. rq '; p ; y,1 a

s,

s g

.. c. p..c.w n, -.

^

t s

"i g

v 2.

3. +

r,, n. m

.. n :

.m.

t

- 1 sf, a{

{> l Y,' l i '

L' 1..

C 4

,4

, s g

l

, ep3. 1,s o,

m.., p,

f

.- 4. (

1 c

r.

y i

i

79. ;cm, _,

I[.

"'l }I.

.)

[/t)

+

m\\'

s

+

t y,

,y

(

[th ~ -

1 3

7. '

i ; \\. -

p Ik.

1%'

,,.hf,

s Q,l -

.K

' !:: %,. m

.qc -c a

.s,

, >, i r si '

i i p)t,-p;:

>g-t L

L

- f

.1

,)'

6

()..A 2 9.

,, s s

i w-f v

lAia p

9 g

g

'g A

g

' Q, 4.'

s g..L>

6

'd,j

.u

> ~~

1 g

p j

4 T

{

-3 r i. '

+

,i yJ ll1,'.

,i,/.

e e l '.

3

.6-.,.,( g

..,.4:1.

i 8

'~.L.

e f

3 g '.c 4

t y

'(

'(

i', f 4

\\

gi.

o"+_

/.

t '1,','1,; g i";o-..

.:v.-

1 t'

s, i s..' 1

("/i.. p l.

, i i

. p i :.,V.,,'.

'.i.. 1 s

t,

n eg+y.

8 c.

+

+

g:,

a

y ;-

i I rg k'

i

.~

g

. )' ; y,.

(%

'1

4..

,5

J, t

t n

7.,.

1

'.i I'..#3

g..

.-'g

,1 -'

• 47

" e r 1' k

iE', '

E i

.g 9,, }, ),

x r

s j

P '.J i,.

t 'r' N

1 ij3" 2'(;.

lf fh,

',' o,

l u,h.:

• l (

h. ;e,

e t

.I i'm j

g '

,,s r

.. v t

.J.,0..'.,#

%r q,

g gi.,.

};.

jy

-s c

V y' yi 3

s4Ji.

t

=d' i

),'

'c g,

i {*')<'

3.

i e

1

(

Y[ ' )),.

4

'1 4,

).q :.

' h,,

f 4

J g'

.t s., )a'

'.W u

>. t

~.

1 h!

.P J

-, '}

W :d P.i -'

1 6

t

[i i

K';

a:

[

k '. 4

{* 12, u:

.g f

A. ;, t 4

t

n. w y

(

r

{r s..

I p- :

Y se 9

'.5,,

)

8 y

s,.

i' s

l',

,lM' 1[ i t!

L o

h g'. s 3;

.J.i

. ge

.!. s i

{,. y ',' V :,,j. (

,L lj

-.-b 4...

Jl,-

Ii C/!?

- f, '., \\)/ '

,o y(.,n. r

u..

u, j,

. g u n%. 3 r.,1 i $

e ',[ H "7

.'(

4'e

-v t h s',) ;- 5,

,. Vs-m.

pss

'J e

I, m

y,,

-. _ = _ _

_... J

I 0* %?b*

O

+N$^C[

Nf

,,,jg/ jM[Odp#,

t IMAGE EVALUATION s kg7 I

TEST TARGET (MT-3) 4@

4

'W'{,9'

/4,,,,

l.O li m Bla y((L24 u

[f GE l31 I.25 t

1.4 1.6 1

4 150mm 6"

4

/<9

>>,g;/,y,,,,,(i sg<g e'

///

o>p {

O

%a-________

.<> +

l

/&g[ l[Md

////g j 4

A IMAGE EVALUATION k///7S/"'. NxNi/#

TEST TARGET (MT 3) g+

+

gy,

+

s I,o lf m ta ti ? Rhh w n l.l

$M bb m

I.25 1.4 1.6 150mm l

4-6"

/4%

..gf,3,,,,,

s-4,y;;g t

ku 1

.A@h E

YA

////gj d

IMAGE EVALUATION

//

TEST TARGET (MT-3)

NT 38 e'4 9

4/,77sig) 99+

g,j<>g g.4 l.0 EFS EE

' ll Fd4 d

u i." M i.s I l.25 1.4 l 1.6-l 4-i50mm 6"

p%g %y7//:

/

4%

//p+3////h n

O MO 4%

$7%

1 J

--y

• 4@@%&c',

///jg/j di

%V IMAGE EVALUATION

+g #

k/g* \\$'

x\\'\\fr/*

TEST TARGET (MT-3)

1. >,/

A*5}g?,

4 Q

l.0

'S m m pljNM 11 ll E5: EM m

I.25 1.4 1.6 4

150mm 6"

1. *g

1. 4%

3 <Q;g4

+1$gf_Ap,,,

ffff7 4

L, v

,N A

p.

~

jh,s' <

g..

l PRES.3JRIZED WATER REACTOR CINERIC FUNDMENTA1A EXAMINATION jh

%?

FURN B t

..,,,f QUESTION:

25.

1 i

Pressure stress on the reactor vessel wall is:

l' A.

' compressive across the entire wall.

B.

tensile across the entire wall.

C.-

tensile at the inner wall, compre'ssive.at the outer wall.

D.

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

l 1

1

)

QUESTION:. 26.

The nil-ductility temperature is that temperature:

A.

below which the probability of brittle fracture significantly increases, f

l B~

wh'ere failure stress becomes greater than the yield stress of the metal, i

C.

below which the probability of plastic deformation significantly.

increases.

D.

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

fracture stress.

L L

iQUESTION:

27.

1' Pressurized.' thermal shock could most likely be a concern during:

A.

an uncontrolled cooldown followed by a rapid repressurization.

l

}

B.

an uncontrolled depressurization followed by a rapid repressurization.

C.=

an uncontrolled cooldown followed by'a rapid depressurization.

l D.

an overpressurization from a low-temperature, low pressure condition.

p.

l QUESTION:

28.

['

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

.A.

accelerated zirconium hydriding.

B.

loss of reactor vessel water level, j,

C.

loss of reactor coolant pump net positive suction head.

c D.

brittle fracture of the reactor vessel.

>l1 FORM B Page 9 of 34 1;

n-f?

g,:.

FRRSSURIZED WATER REACTOR GENERIC PVNDAMENTA1.S EXAMINATION FORM B I

[..

' QUESTION:

29..

j The' primary purpose of a pressure relief valve is to:'

'A.-

maintain system flow, t

B.'

maintain system pressure.

C.-

maintain system integrity.

D..

maintain system temperature.

QUESTION:

30.

When a discharge valve is opened to atmosphere, the pressure on the upstream r

side of the valve will:

j A.

remain the same, and the pressure on the downstream side will increr.se.

5 B.

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

C.

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

D.

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

?

QUESTION:

31.

The function of a valve backseat is to:

A.

isolate system pressure from the packing and stuffing box to minimize packing leakage.

B.

isolate system pressure from the packing and stuffing box for the purpose of valve repacking.

.l 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.

1; i

l l

FORM B Page 10 of 34 l-

~.

PRESSURIZED WATER REACMR CENERIC FUNDAMENTALS EXAMINATION FORN &

i 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 C.

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

Actuation of the valve actuator motor in either the open or close direction QUESTION:. 33.

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

i A.

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

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 l

one-half turn using normal force.

l l

QUESTION:

34.

1 l'

Density compensation is used in flow instruments to change to A.

mass flow rate, volumetric flow rate L

B.

volumetric flow rate, mass flow rate l

l C.

fluid pressure, volumetric flow rate l'

l D.

differential pressure, mass flow rate 1

1 1

l l

i l

l FORM.B Page 11 of 34 l-

x

w'

, FRE85URIEED UATER REACTOR CENERIC FUNDAMENTAIA EIAMINATION FORM B i

QUESTION:

35.

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

)

voids'(gas or steam),, indicated flow rate will be i

'A.

erroneously high.

j

.B.

. erroneously low.

C.

unaffected.

D..

fluctuating.

t QUESTION:

36.

n,.

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

A.

. increase slightly.

B.

decrease slightly.

C.

go to zero.

D.

not change.

[

^;

QUESTION:

37.

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

A.

DIRECTLY proportional to the differential pressure.

B.

INVERSELY proportional to the differential pressure.

l C.

DIRECTLY proportional to the square root of the differential pressure.

D.

INVERSELY proportional to the square root of the differential pressure, p

F

.{

FORM L Page 12 of 34 t

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

FRESSURIEED WATER REACTOR GENERIC FUNDMGNTA1A EXAMINATION j

y FORK B l

J

QUESTION

38.

I

)

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

l

'A.

DIRECTLY proportional to the height of the variable leg.

[

B.-

INVERREEY proportional to the height of the variable leg.

-C.

DELEcrEY proportional to the density of the reference leg.

D.

INVERREEY proportional to the temperature of the reference leg.

i h

,f QUESTION:

39.

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

A.

read less than actual level.

B.

read greater than actual level.

C.

equal the actual level.

D.

slowly decrease to zero, i

QUESTION:

40.

The output for a reference leg differential pressure level instrument will fail LQN as a result of:

A.

a break on the reference leg.

I B.

a rupture of the diaphragm in the differential pressure cell.

l C.

the reference leg flashing to steam.

'D.

a break on the variable leg.

l 1,

l L

l l

l L

1:

l l

FORM B Page 13 of 34 L,

o r

e a

j.

PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION FORN &

QUESTION: -41.

0 l

l 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.

8.

two dissimilar metals is INVERSELY proportional to the temperature change li.

measured at their junction, 4

C.-

a metal is DIRECTLY proportional to its change in temperature.

1 D.

a metal is INVERSELY proportional to its change in temperature.

1 QUESTION:

42.

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

If transmitter I is calibrated at 200 degrees i and transmitter II is j

calibrated at 100 degrees F, then at 150 degreen F:

A.

transmitter I will read greater than transmitter II.

B.

transmitter II will read greater than transmitter I.

O.

transmitter I and II will read the same.

i D.

it is 'spossible to predict how either transmitter will respond.

QUESTION:

43, a

Scintillation detectors operate on the principle of:

i A.

photodisintegration.

i B.

photokinesis, i

l-C.

photomultiplication.

D.

photoionization.

l l

I j,

l~

1 7

l i

l l

l FORN B Page 14 of 34 l

1.

PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION FORM B QUESTION: 44 i

A BF3 proportional counter detects both neutrons and gammas. Which of the following best describes the method used to eliminate the gania contribution from the detector output?

A.

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

The outputs are electrically opposed to cancel the gamma induced cucrents and yield a neutron only signal for indication use.

B.

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

C.

Gamma induced detector pulses are of it, sufficient 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.

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.

- r 5

QUESTION:

45.

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

A.

gain.

B.

bias.

C.

feedback.

D.

error.

l I

f QUESTION:

46, 1

l-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 reSulator, s

C.

a positioner.

l D.

an amplifier unit.

l FORM B Page 15 of 34 l

l m

,,>y.

y.

.y

-.%,.p

+

yg~

w

' PRESSLRIZED WATER REACTOR CENERIC FUNDAMENTALS EKAMINATION FORM B m

QUESTION: 47.

Why must an operator pay particular attention to auto / manual valve controllers left in the manual mode?

A.

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

mode, e

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 position.

D.

The valve can only be operated locally during this time.

i n

QUESTION:

48.

What precautions must be observed when transferrin 6 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 val.e controller output signals are matched between automatic mode and manual mode.

C.

Ensure that the valve controller stabilizes in the automatic wode 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.

QUESTION:

49.

An indication of centrifugal pump cavitation is:

A.

pump motor amps pegged high.

B.

pump discharge pressure indicating zero.

C.

pump motor amps oscillating.

D.

pump discharge pressure indicating shutoff head.

P l

FORM B Page 16 of 34 l

M+:

i

. S.:

PRESSURIZED. WATER REACTOR CENERIC FUNDAMENTALS EXAKINATION yogg g

.y

1. t x

l 50.

l

. QUESTION:

18 The term " shutoff head" for a centrifugal pump indicates that it is pumping.-

S:

at:

l' y

}

'A.

maximum capacity and minimum discharge head, r

L B.

' maximum capacity and maximum discharge head.

C.

minimum capacity and maximum discharge head,

.D.

minimum capacity and minimum discharge head.

QUESTION:

51.

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

4 QUESTION:- 52.

SHUTTING the discharge valve on an operating centrifugal pump will cause the MOTOR AMPS to and the pump DISCHARGF, PRESSURE to A.

. increase, increase

)

'B.

decrease, increase C.

increase, decrease t

D.

decrease, decrease L

i 4

FORM B Page 17 of 34 9

)

,-w.

e.

a-e

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

,n..

v.c.--,

-,--n

n u

_y FRESSURIEED WATER REACTOR GENERIC. FUNDAMENTALS EXANINATION -

PORN B

[g.

s..

QUESTION:

53.

If the speed of a positive ' displacement pump is increased, the available net positive suction head (NPSH) will and the probability of cavitation will I

~A.

..increaue, increase

~

- B ~.

decrease, decrease C.

. increase, decrease D.

decrease, increase t

QUESTION:

54.

Reactor coolant pump 'notor amps will,

if the rotor is IDCKED and the motor speed will-if the rotor H ERS.

A..

increase, increase B.

increase, decrease C.

decrease, increase D.

decrease, decrease i '.

QUESTION:

55.

1 1

~If the generator bearings on a motor generator overheat then:

L A.

.the generator voltage will increase.

i l.

B.

the generater windings will overheat.

l l

C.

the motor current will decrease.

D, the motor windings will overheat.

L FORN B Page 18 of 34 t

i..

.~.o.

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

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

a.

3--

< PRESSURIZED WATER REACTOR CENERIC FUNDAIGNTAIJ EKANINATION

.t' PORK B I

QUESTION

56.

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

ii~

A.

remain constant.

. B.' -

increase two fold (double).

'C.

. increase four fold.

D.

increase eight-fold.

QUESTION:

57.

The starting current in an A.C. motor is significantly higher than the full-load running current because:

A.

" starting torque is lower than running torque.

B.

starting torque is higher than running torque.

lC.

rotor current during start is higher than running current.

i D.

rotor current during start is lower than running current.

' QUESTION:

56.

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.

B.

excessive torque is generated during motor start.

C.

running current is much higher than starting current.

D.

rotors are normally started under full load conditions.

e FORM B Page 19 of 34

I p

O.

PRESSURIEED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION' j

PoaN B-3, 1

QUESTION:

59.

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

- distributed temperature reduction is a description of:

)

)

- A.

heat stress -

i B.

thermal shock.

)

C.

~ thermal strain, i

j D.

heat strain, QUESTION:

60.

'?

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 throu5h the tube side of the exchan5er.

C.

reducing the overall (total) heat transfer coefficient.

D.

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

. QUESTION:: 61..

Borsted water is flowing through the tubes of a heat exchanger being cooled by fresh water.. The shall side pressure is less than tube side pressure.

What will occur as a result of a tube failure?

A.

Depletion.of borated water inventory.

B.

Depletion of cooling water inventory.

t ll C.

Dilution of'the borated water system.

i.

D.

Shell pressure will decrease.

l I

l.

l 1

1.

l l

PORM B Page 20 of 34 1

1

',h -

L

o 6 :.;

?

k PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EIAMINATION

~

P PORM B -

)

E3 ff ' '

QUESTION:

62.

s.

, 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 dramatically increased.

f.

C.

Organic compounds used as resins will decompose.

D.

The creation of preferential flowpath through the demineralizer will occur.

. QUESTION:

63.

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

+

A.

Increases pressure drop across demineralizer B.

Increases flow rate through domineralizer C.

Increases demineralizer outlet conductivity-D.

Increases domineralir.er inlet pH QUESTION:

64.

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

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

A.

Temperature of the coolant passing through the demineralizer has decreased.

B.

,pH of the coolant has increased significantly.

C.

Flow through the deborating resins has increased sharply.

D.

Deborating resins have become boron saturated.

FORM B Page 21 of 34

~...

m,

)..

.q

, PRESSURIZED WATER'RIACTOR GENERIC FUNDAMENTALE EKAKINATION FORM B h....

QUESTION:

65.

"To'de' energize 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.

[ QUESTION:

66.

To ensure reliable local breaker indication is being provided the l'

must be reset after breaker operation.

+

L A.

OPEN/ CLOSED mechanical flag B'

OPEN/C1DSED indicating lights C.

Overcurrent trip flag D.

. Spring. CHARGE / DISCHARGE flag L

l' QUESTION:

67.

1 L

A circuit breaker thermal overload device:

A.

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

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.

D.

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

4 FORM B Page 22 of 34

....~......

7 y --

V, PRESSURIZED WATER REACTOR' GENERIC FUNDAMENTALS EXAMINATION FORM B l

QUESTICN:

68.

Loss of circuit breaker control power will cause:

A.

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

B.

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

C.

inability to operate the breaker locally and remotely.

D.

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

breaker, QUESTION:

69.

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

A.

an overvoltago condition will occur on the bus.

B.

an overcurrent condition will occur on the generator.

C.

an overvoltage condition will occur between generator phases.

1 l

D.

generator undervoltage relay actuation will occur, j

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.

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.

I FORM B Page 23 of 34

[y,

[,. '.~. '

P-s s

7-

- PRESSURIEED WATER REACTOR CENERIC MINDAMENTALS EXAMINATION L-FORM S

-QUESTION:

71, t

(

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.

C.

overcurrent.

D.

overspeed.'

QUESTION:

72.

The ' operator has just pulled controi 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.

subcritical j

4 FORM B Page 24 of 34 6

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

.e--,,

-,,. ~, ---

+, - -,

-,,,r-

---

,-me

- 3

,b1'idi i

b FRESSURIEED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION i

F PORN 5 H

1 I

.QUESTIONi 73.

J The ratio of the number of neutrons in one generation to the number of j

neutrons in the previous generation is the:

A.-

' effective multiplication factor 1

B.

fast fission factor I

C.

neutron non leakage factor l

4

'D.

neutron reproduction factor i

')

QUESTION:

74.

Reactivity is defined as the

i A.

fractional change in neutron population per generation.

B.

number of neutrons by which neutron pcpulation changes per generation.

C.

rate ~sf change of reactor power in neutrous per second.

D.

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

t l

QUESTION:

75.

A given amount of positive reactivity is addsd to a critical reactor in the source.(startup) range.

The amount added to less than the average effective l

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 neutrou lifetime B.

Fuel temperature coefficient t

C.

Average effective decay constant D.

Moderator temperature coefficient l

i.2 L

FORM B Page 23 of 34 1

M

'8 FRESSURIEED WATER REACTOR GENERIC FUNDAMENTA13 EXAMINATION FORN 5 e

i QUESTION:- 76, Over core life the production of plutonium isotopes with delayed neutron a

fractions than uranium delayed neutron fractions will cause reactor power transients to be near the end of core life.

J A.

less,' faster' B.

less, slower C.

greater, faster D.

greater, slower QUESTION:

77.

t An. installed neutron source:

A.

maintains the production of neutrons hi h enough to allev the reactor to 5

+

achieve criticality.

B.

'provides a means to allow. reactivity changes to occur in a subcritical reactor.

1 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.

' QUESTION:

78.

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

A.

Reactor coolant temperatute increases result in a larger increase in the 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 non-leakage probability.

D.

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

4 i

FORM B Page 26 of 34

[

.n PRESSURIZED WATBt REACTOR CE"TERIC FUNDAMENTitLS EKAMINATION FORM B e

QUESTION:

79.

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

A.

As reactor power increases, the rat 6 of increase in the fuel temperature diminishes.

B.

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

C.

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

D.

The amount of Dopplar broadening per degree change in fuel temperature diminishes, t

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.

A.

an integrated, total B.

a rate of, differential C.

a differential, total D.

a total, difierential QUESTION:

81.

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 B Page 27 of 34

~

Y YRESSURIZED WATER REACTOR CENERIC FUNDAMENTA1A EKANINATION FORN R a

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 corn.

B.

moderator temperature coefficient decreases, causing decreased competition.

C.

fuel temperature increases, decreasing neutron absorption in fuel.

J D.

decreased moderator density increases neutron migration length.

QUESTION:

83.

Control rod (CEA) bank overlap:

A.

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

B.

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

C.

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

D.

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

QUESTION:

84.

l l

The basis for the maximum power density (kw/ft) power limit is to:

l l

A.

prevent fuel clad melt.

B.

prevent fuel pellet melt.

C.

limit bulk coolant temperature.

D.

prevent nucleate boiling.

FORM B Page 28 of 34

V:

?

i h

' FRESSURIZED WATER REAC'!OR CENERIC FUNDAMENTALS EEAMINATION PORM B

[

QUESTION:

85.

The control rod insertion limits are power-level dependent because the magnitude of:

A.

control rod worth decreases as power increases.

F.

power defect increases as power increases.

C.

Doppler (fuel temperature) coefficient decreases as. power increases.

D.

moderator temperature coefficient increases as power increases, t

QUESTION:

86.

1 Fission products that have substantial neutron capture cross sections are:

A.

excited fission products.

B.

fission product daughter.

C.

radioactive fission products.

D.

fission product poisons.

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.

l 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.

i l

l l..

i l'

l l

l L

l FORM B Page 29 of 34

r g

f PRESSURIEED WATER REACTOR CENERIC FUNDAMENTAIJ EIANINATION PORN 5 c ;.

QUESTION:

88.-

Following a reactor trip from sustained high powar operation, the major Xenon

]

135 removal process is:

]

A.

' ion exchange.

1 B.

heta decay.

C.

' neutron capture.

D.

alpha decay.

QUESTION:

89.

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 will:

1 A.

be twice the 50 percer.t value.

B.

be less than twice the 50 percent value.

C.

be more'than twice the 50 percent value.

D.

remain the same since it is independent of power.

l

' QUESTION:

90.

s 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:

c L

l A.

Xenon peaking.

L B.

Xenon override.

K C.

Xenon burnup.

D.

Xenon oscillation.

i i

L 3

FORN B Page 30 of 34

'N--

y

~,..n n,

,.,,,.m,_w-,,,-

e.,

s

e PRES 8URIEED WATER RNACTOR GENERIC FUNDAMENTALS EXAMINATI0lt.

d FORM B

. d o'

QUESTION: 91.

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

[

. power to 50 percent. Xe-135 will reach a i.:v equilibrium condition in 1

hours..

4 A.

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

.20 to 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> 36 C.

30 to 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> D.

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

~

QUESTION:

92.

The reactor is near the end of its operating cycle.

In order to stay critical, power and temperature have been allowed to "coastdown." Why is boron no longer used to compensate for fuel depletion?

I A.

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

l B.

, The differential boron worth has decreased below its useable point, j

C.

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

l D.

"Coastdown" is preferred due to fuel conditioning limitations.

QUESTION:

93.

1s 1

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

A.

Count rate will' increase slightly.

B.

Count rate will double.

C.

The reactor will remain suberitical.

D.

The reactor will be critical or slightly supercritical.

FORM B Page 31 of 34

.u

+

^

s.

s

'i IRESSURIZED WATER REACTOR CENERIC FUNDAIGDITAIE EEANINATION FORM B

'I QUESTION: 94.

j q

,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.

I B.

supercriticality.

1 C.

suberiticality.

D.

equilibrium subcritical count rate.

QUESTION:

95.

l i

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

four. hours after a trip from 100 percent power equilibrium conditions.

The actual critical rod (CEA) position will be LOWER than the predicted critical rod (CEA) position if:

A.

the startup is delayed until eight hours after the trip.

B.

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

'startup.

l L

C.

actual boron' concentration is 10 ppm more than the assumed boron L

concentration.

1 D.

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

t QUESTION:

96.

f 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)

C.

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

D.

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

FORN B Page 32 of 34

e y

a,

+

+

o;,

c PRESSURIZED WATER REACTOR CENERIC PUNDAAENTALS EKANINATION t,

.o..

PORN 5 y

te QUESTION:

97.

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

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

n

. critical.

' A ~. 4 I

' B.

supercritical.

g C.

suberitical, a

r-

' D.'

prompt critical.

c.

,s QUESTION:

98.

Given a critical reactor operating below the point of adding heat, what j

reactivity effects are associated with reaching the point of adding heat?

f A.

There are no reactivity effects since the reactor is critical.

B.

The increase in fuel temperature will begin to create a positive j

, reactivity effect.

v C.

The decrease in fuel temperature will begin to create e negative 1

reactivity effect.

' D.

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

t p:

, QUESTION:

99.

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

_ seconds.

[.

A.

.360 l-l

- B.

270 h

C.

180 l

.c D.

90

!l l

p l

I U

FORM B Page 33 of 34 a;

.c 6.,,..

o 4

r 1

, y" y, h FRESSURIZED WATER REAC70R GENERIC FUNDAMENTALS EXAMINATION PORN B' o

QUESTION:

100.

4,4- 'The major reason boron is used in s' reactor is to permit:

e

.A.

a reduction in the shutdown margin.

B.

an. increase in the amount of 6ontrol rods (CEAs). installed.

C.

an increase in core life.

'D.

a reduction in the effect of resonance capture.

e i

i S'

I l

l l

l l

l-i l,

l.

l.'

1.

l l

l l

t

?:

l 4

o FDRM E Page 34 of 34

.....m

-