ML20033F026

Forwards Answer Keys,Grading Results & Individual Answer Sheets of Examinees for Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 900207

ML20033F026
Person / Time
Site:	FitzPatrick
Issue date:	03/05/1990
From:	Gallo R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Simpson D POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
NUDOCS 9003150283
Download: ML20033F026 (88)

Text

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IAAR 5 1990 i

Docket No. 50-333 i

Power Authority of the State of New York

~

I.

James A. FitzPatrick Nuclear Power Plant ATTN: Mr. O. Simpson s

L Superintendent - Training P. O. Box 41 Lycoming, New York 13093 l

Dear Mr. Simpson:

I On February 7,1990, the NRC administered a 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 taking the L

examination from your facility.

Please forward'the results to the examinees along with the copies of their answer sheets. A "P" in the column labeled RESULTS indicates a passing grade for this examination.

Passing Grade for the MLS 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 Public Document Room.

The results for individual examinees are exempt from disclosure; therefore, enclosures (3).and (4) will not be placed in NRC's Public Document Room.

L Should you have any questions concerning this examination, please contact Mr. Richard J. Conti at telephone number'(215) 337-E210.

Sincerely, i

0,t eW1 SiEnod BYt Robert M. Gallo, Chief Operations Branch Division of Reactor Safety

Enclosures:

1.

Examination Form "A" with answers and references 2.

Examination Form "B" with answers and references 3.

Examination Results Summary for Facility 4.

Copies of Candidate's individual answer sheets cc w/o encis:

J. Phillip Bayne, President I

W. Fernandez, Resident Manager h

J. Brons, Executive Vice President i

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9003150283 900305

?

PDR ADOCK 05000333 V

PDC

$5

mm i

[

r Power Authority of the State of 2

New' York i

cc w/o encls. cont'd.:

.A. Klausmann, Senior Vice President - Appraisal and Compliance Services R. Patch, Quality Assurance Superintendent G.-Wilverding, Manager Nuclear Safety Evaluation G. Goldstein, Assistant General Counsel R. Beedle, Vice President Nuclear Support S.-Zu11a, Vice President Nuclear Engineering R. Burns, Vice President Nuclear Operations J. Gray, Director Nuclear Licensing - BWR i

Dept. of Public Service, State of New York l

State of New York, Department of Law Local Public Document Room (LPDR)

Nuclear Safety Informati9n Center (NSIC)

NRC Resident Inspector State of New York, SLO Designee i

cc w/ enc 1s. I and 2:

Public Document Room (PDR) bec w/o encls.:

Region I Docket Room (with concurrences)

Management Assistant, DRMA J. Linville, DRP.

D. Limroth, DRP D. LaBarge, NRR J. Dyer, EDO OL Facility File t

d DhdTES DRS:RI Curley/aj k Gally /90 D(/c'/90 02/g d

to 03 k

OFFICIAL RECORD COPY FL/50-333/2/27/90 - 0002.0.0 02/27/90

3 s

j ENCI.DSURE 1 j

i CENERIC FUNDAMENTALS EXAMINATION SECTION (CFES)

BOILING WATER REACTOR FORM A i

e t

i e

t k

l i-ENCLOSURE 1

't 4

FEBRUARY 1990 BWR GFE - FORM A ANSWER KEY 1.

DELETED 26.

A 51.

D 76.

A 2.

A 27.

A 52.

A 77.

C 3.

C 28.

C 53.

D 78.

B 4.

A 29.

B 54.

C 79.

C 5.

B 30.

A 55.

DELETED 80.

B 6.-

D 31.

D 56.

C 81.

B 7.

C 32.

B 57.

A 82.

A 8.

A 33.

D 58.

D 83.

B 9.

D 34.

C 59.

C 84.

B 10.

C 35.

A 60.

B 85.

D 11.

A 36.

B 61.

D 86.

C 12.

D 37.

C 62.

B 87.

A 13.

A 38.

D 63.

C 88.

C 14.

B 39.

A 64.

A

9.

D 8

15.

C 40.

A 65.

A 90.

C 16.

B 41.

B 66.

D 91.

B 17.

C 42.

A 67.

A 92.

C 18.

A 43.

D 68.

C 93.

B 19.

A 44.

C 69.

B 94.

C 20.

D 45.

C 70.

A 95.

A l

21.

C 46.

A 71.

C 96.

A 22.

B 47.

A 72.

B 97.

A 23.

D 48.

A 73.

A 98.

B l

24.

D 49.

B 74.

DELETED 99.

D l

25.

D 50.

B 75.

A 100.

C L

i e'

4

u

?

l BWR FORM A i

RULES AND CUIDELINES FOR THE s

CENERIC FUNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:

l (1)

Print your name in the blank provided on the cover sheet of the i

examination.

(2)

Fill in the name of your facility.

(3)

Fill in the ID Number you were given at registration.

(4)

Fill in your start and stop times at the appropriate time.

(5)

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

(6)

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

Follow the instructions for filling out the answer sheet.

(7)

Scrap paper will be provided for calculations.

(8)

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

(9)

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

Cheating could also result in severe penalties.

(10) 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.

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

(12) Turn in your examination materials, answer sheet on top, followed by the exam booklet, then examination aids - steam table booklets, handouts and l

scrap paper used during the examination.

1 L

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

as defined by the examiner.

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

BWR FORM A L

1

1

.v.

l

,i EQUATION SMEET Cycle Efficiency Nat Verk (out) e e

- ac AT Q

Energy (in) p 6

S/(1 K,gg) a Ah SCR 6 " - UA AT CR3 (1 Kett)1 CR2 (1 - Kett)2 I

CRg/CRo j

1/(1 K,gg)

SUR - 26.06/r, M

26.06 (LrtA II

• Ertt10 M

=

sa.

(p. p)

(1. g,,,) 3 (1

K rt)/Kett Po 10 **)

SDM 8

P e

Wg a t t )

Po e Pwr P

2*/(P k)

.j (2*/p) + ((i P)/Aef tP) f f

1 x 10*S seconds 1)/K rt 1

(K,gg p

o AK,gg/K,gg A,gg - 0.1 seconds *1 p

=

9 2.21 lba

]

3.7 x 1020 dps 1 kg 1 Curie 3.41 x los BTU /hr 2.54 x 1088TU/hr 1 Mw 1 hp 9/5 *C + 32 778 ft-lbf

'F 1 BTU 5/9 ('F 32)

'C m

J e

i I

BWR FORN A QUESTION: 1

)

Which of the following statements describes the operation of reactor pressure vessel safety valves?

A.

%n the activating pressure for a safety valve returns to the lift setpoint, a combination of air and steam pressure closes the valve.

B.

As reactor pressure increases to the lift setpoint, the pressure overcomes spring tension on the valve operator, causing the valve to fully open.

C.

As the disk on a safety valve lifts, less pressure is exerted on the disk, reducing the upward force on the disk, and thereby regulating the valve position.

D.

When the safety valve lift setpoint is reached, a pilot valve opens allowing reactor pressure to fully open the main valve disk.

l-i QUESTION:

2 If a pressure control valve at the outlet of a heat exchanger is opened, system t

flow rate will and head loss will A.

increase; decrease l

l.

B.

increase; increase C.

decrease; decrease l

l D.

decrease; increase i

QUESTION:

3 All of the following are acceptable methods for verifying the position of a SEZI manual gate valve, EXCEPT:

A.

observing the position of the valve stem using handwheel or position indicators.

B.

observing indicators for plant parameters, such as temperature, pressure and level.

C.

attempting to turn the handwheel in the "open" direction.

D.

attempting to turn the handwheel in the " closed" direction.

BWR FORM A 1

.m

F i

2 BWR FORM A 1

i F '

QUESTION:

4 i

The manual declutch lever of a motor operated valve the motor and

__ the handwheel.

A.

disengages; engages

{

B.

doenergizes; engages C.

engages; disengages D.

reenergizes; disengages

'l QUESTION:

5 Check valves are used to:

A.

relieve system overpressure, thereby ensuring system integrity.

B.

prevent backflow throu6h non operating components or flowpaths.

C.

maintain a constant backpressure to control flow rate.

D.

prevent pump cavitation by keeping systems full of liquid.

I QUESTION:

6 Operators should use ASIH hands on valve handwheels when positioning manual valves to:

A.

overcome the resistance of installed locking devices.

[

1 B.

control the rate of valve motion to prevent water hammer.

l I

C.

ensure system pressure, temperature, and flow are controlled during valve L

motion.

l-l D.

control lateral force to prevent bending the valve stem.

v 7

BWR FORM A 2

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BWR FORM A I

QUESTION:

'7 I

E Which one of the following failures of a wet reference leg differential pressure (D/P) level. transmitter will cause its level indicator to indicate the LDVEST level?

A.

The D/P cell diaphragm ruptures.

B.

The reference leg ruptures.

O C.

The variable leg ruptures, i

D.

The equalizing line ruptures.

QUESTION: 8 i

If a resistance temperature detector (RTD) develops an QZEH circuit (bridge circuit remains intact), indication will fail:

i A.

high.

B.

low.

l C.

as is.

~

D.

to mid scale.

QUESTION: 9 A differential pressure level transmitter' with its; reference leg vented to L'

atmosphere is being used in a control loop to maintain liquid level in a vented tank at 50 percent. The transmitter was calibrated at a tank temperature of 200 P

degrees F.

If the tank temperature gradually falls to 100 degrees F, the control loop will.cause ACTUAL level to:

A.

be maintained at 50 percent.

B.

increase and remain above 50 percent.

C.

first' increase, then decrease to 50' percent.

D.

decrease and remain below 50 percent.

BWR FORM A 3

o a:,. -

BWR FORM A i

' QUESTION:

10 A simple bellows pressure detector is located in the reactor containment with its. low pressure side vented to the containment.

If a main steam break raises

+

conceinment pressure by 40 psig, the associated pressure indication (disregarding any temperature effect on the bellows) will:

A.

increase by the square root of 40 psig.

B.

increase by 40 psig.

'l C.

decrease by 40 psig.

D.

stay constant.

. QUESTION:.11 A differential pressure (D/P) cell is being used to measure flow rate in a cooling water system. Flow rate is indicating 75 percent of scale. If the D/P cell diaphram ruptures, INDICATED flow rate will:

A, go to O percent.

B..go to 100 percent (full scale).

C.

remain the same.

i

'D.

move slowly to 50 percent (mid scale).

(

2 QUESTION:. 12 A bourdon tube pressure detector that is indicating 50 percent of scale is suddenly exposed to a pressure transient that extends the detector 75 percent beyond its upper range value. ' Actual pressure returns to its original value, i

Assuming the detector remains intact, the affected pressure indication will initially go off scale high, and then:

A.

become unpredictable until the instrument is calibrated.

B.

return to a pressure less than original pressure.

.C.

. return to original pressure.

D.

return to a pressure greater than original pressure.

BWR FORM A 4

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- - L.-

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+ -

w

1 1

BWR FORM A i

QUESTION:

13

.{

-i Most'of the electrons collected in a fission chamber are released as a result i

of ionizations caused DIRECTLY by:

'l

.A.

fission fragments.

\\

B.

fission gammas.

I C.

fission betas.

D.

' fissionable materials.

i QUESTION:

14 Which of - the following statements describes the use of a self reading pocket dosimeter (SRPD)?-

l A.

SRPDs hold their charge indefinitely when removed from a radiation field, i

B.

SRPD readings must be considered inaccurate when they are dropped.

I C.

SRPDs can be used to record beta and gamma radiation.

j D.

The output of an SRPD is a dose rate in ar/hr.

-QUESTION:

15 The range of values around the setpoint of a measured variable where NO ACTION i

occurs in an automatic flow controller is called:

i A.-

deviation.

B.

error.

C.

deadband.

D.

bias, h

r i

BWR FORM A 5

t

k l

i BWR FORM A i

QUESTION:

16 i

The governor of an emergency diesel generator (D/G) DIRECTLY senses D/G l

and adjusts D/C flow to maintain a relatively constant l

D/G frequency.

i A.

load, air f

B.

speed, fuel l

C; load, fuel L

D.

speed, air i

I

=

QUESTION: 17 The output pressure of a pneumatic controller is typically insufficient to drive a valve actuator accurately.

To overcome this problem, a control loop would NoltMALLY employ a:

t A.

valve actuating lead / lag unit.

(

B.

pressure regulatdr.

t C.

valve positioner.

D.

filter drive unit.

l t

QUESTION:

18 Which of the following changes in pump operating parameters will DIREQTLY lead to pump cavitation in a centrifugal pump that is operating in a closed loop system?

A.

Steadily increasing pump inlet temperature.'

5.-

Steadily decreasing pump flow rate (by reducing pump speed).

l C.

Steadily increasing pump suction pressure.

D.

Steadily increasing pump discharge pressure.

BWR FORM A 6

i 37

=. -

BWR FORM A

~

QUESTION:

19 i

Cas binding in a centrifugal pump can be prevented by prior to pump start.

i A.

venting the pump l

I B.

Iowering suction pressure C;

throttling the discharge valve

-}

.D.

shutting the discharge valve f

QUESTION:

20 i

The correct way to start most M actor. driven centrifugal pumps is with the pump discharge valve:

1 A.

in any position.

-)

B.

throttled to aidposition.

i i

C.

fully open.

I i

D.

fully closed, f

QUESTION: 21 i

A multispeed centrifugal pump is operating at 1900 rps, providing a flow of 400 gpa at.20 psig.

If the pump speed is increased to 3600 rpa, the new pump discharge pressure will be:

A.

20 psig P

B.

40 psig l

C.

80 psig

[

1 u,

D.

160 psig L

l 5

l BWR FORM A 7

N D

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' a BWR. FORM A l

_ UESTION: 22 Q

- Which one of the following conditions will result in a REGEE&EE in the available recirculating pump not positive suction head (NPSH)?

A.

Carry under decreases.

B. -Recirculation flow rate increases.

C..

Feedwater inlet subcooling increases.

D.

Feedwater flow rate increases.

I QUESTION:

23 A constant speed centrifugal pump motor draws the LEAST current when the pump is:

A.

at runout conditions.

B.

at operating conditions.

i C.* accelerating to normal speed during start.

D.- at shutoff head.

l QUESTION:

24 Failure' to provide adequate minimum flow for a centrifugal pump can DIRECTLY result in:

A.

discharge piping overpressurization.

B.-

suction piping overpre,ssurization.

C.

~ excessive pump leakoff.

D.

pump overheating.

1 BWR FORM A 8

s

l 5

-q g

p BWR FORM A QUESTION: 25 r.

6 A centrifugal pump is operating at rated conditions in a closed systen with all

(

valves fully open.

If the pump suction valve is TlHLOTTLED to 50 percent, pump i

' discharge pressure will and flow will l

'A.-

increase; decreate I

B.

decrease; increase

'C.

increase; increase 1

D.' decrease; decrease QUESTION:

26

+

i The main generator is connected to the grid.

Which of the following i

characteristics will an IDIDEREICITED generator exhibit?

I A.. Negative negavars (vars in) and a leading power factor B.

Positive negavars (vars out) and a leading power factor C. -. Positive negavars (vars out) and a lagging power fact.or -

D.

Negative negavars (vars in) and a lagging power factor QUESTION:

27 A centrifugal pump has a flow rate of 3,000 gpm and a current requirement' of 200 amps. If the speed is reduced such that the flow rate is 2,000 gpm, what is the final CURRENT requirement at the new lower speed?

(Assume a constant motor voltage.)

A.-

59 amps B.

89 amps C.

'133 amps D.

150 amps BWR FORM A 9

4 m

o i

i.

(.c swr FORM A

{_

QUESTION:

28 Which of _ the following is the reason for LIMITING the number of motor starts in

}

a given time period?

l A.

Minimizes pitting of starter contacts f

B.

Prevents excessive torsional stresses on motor shaft i

C.

Prevents overheating of motor windings D.

Minimizes axial stresses on motor bearings 6

QUESTION:

29 If a locked rotor occurs on an operating motor driven pump, motor amps will:-

i A.

increase due to the decreased pump flow.

B.

increase due to the increased mechanical load.

C.

decrease due to the decreased pump flow.

D.

decrease due to the increased mechanical load.

l QUESTION:

30 i

When placing a heat exchanger in service, care must be taken to introduce both fluids gradually and simultaneously to:

A.

prevent excessive thermal stresses in the heat exchanger.

B.

maximize heat exchanger efficiency.

L C.

minimize fouling of the heat exchanger tubes.

D.

provide maximum control of cooling water outlet temperature.

b

~

BWR FORM A 10 e

m m.

o i

y BWR FORM A QUESTION:

31 Refer to the figure below for the following question. All valves are identical

{

and are initially 50 percent open.

To LWEA the temperature at point 7, the operator should adjust valve i

in the QPH direction.

A.

A e

t 8.

8 t

C.

C i

i D.

D I

~

al3,5.

{.

[,

k t

em4 i

e 3 i

t',,-

][c h

6.,

-,w 13 4,,y h

4 I

BWR FORM A 11

[.

4 BWR FORM A QUESTION:

32 The M6191 thermodynamic concern resulting from RAFIDLY cooling a pressure vessel f

'is:

A.

loss of subcooling margin.

r B.

thermal shock, i

. C.

loss of shutdown margin.

D.

condensation.

I r

QUESTION:- 33.

i During normal reactor operation, a main condenser develops an air leak which decreases ' vacuum at a rate of 1 in. Hg/ min.

Which of the following plant parameters would be the FIRST to show en INCitEASE because of this condition?

A.

Extraction steam flow i

i B.

. Generator megawatt output C.

Circulating water outlet temperature

[

D.

Condensate temperature l

t

)

l.,%

+

h r

BWR FORM A 12 e

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-- +

. 1

BWR FORM A QUESTION:

34 Refer to the figure below for the following question.

Which of the following effects would occur as a result of a tube FAILURE in the heat exchanger?

A.

High pressure fluid inventory increases.

B.

Flow in the low pressure system reverses.

,C. Temperature in the low pressure system increases.

D.

IAvel in the tank increases.

pumpers wh&

W 1'

6 s

anoo nas o

1 E

O e

e 6

o BWR FORN A 13

t BWR FORM A i

l

. QUESTION:

35.

1 i

l Proper venting of a shell and tube heat exchanger is important because an air bubble:

A.

reduces the heat transfer ability of the heat exchanger.

B.

causes pressure transients within the tubes as heat load. changes.

C.

causes thermal shock as it moves through the heat exchanger.

D.

causes flow restriction within the heat exchanger.

QUESTION:

36 j

Channeling in a desineralizer is undesirable because:

{

A.

resin beads will slump to the bottom of the domineralizer causing a flow blockage.

]

B.

portions _of the resin will be completely bypassed causing outlet conductivity to increase.

C.

the resulting high velocity fluid flow causes erosion of the resin beads I

and the release of ions.

i D.

the resulting high velocity fluid flow can cause mechanical damage to l

system piping and components.

QUESTION: '37 J

The buildup of scale on heat transfer surfaces in the reactor vessel:

A.

results in lower fuel temperature, which decreases the nuclear fuel cycle efficiency.

B.

is controlled by complying with core thermal limits and adhering to fuel preconditioning requirements.

C.

~is controlled by using reactor water cleanup unit (RWCU)

• system and condensate system demineralizers.

D.

results in higher coolant temperature, which increases eterall plant efficiency.

BWR FORM A 14

I BWR FOPWI A QUESTION:

38 The temperature of the water passing through a domineralizer must be controlled because EXCESSIVELY HOT water:

j i

A.

retains impurities, thereby reducing ion exchange.

B.

is less dense, allowing less water to flow through the resin bed.

C.

will result in domineralizer retention element thermal expansion, thereby releasing resin.

l D.

will result in domineralizer resin dscomposition, thereby reducing resin effectiveness.

l QUESTION:

39 A result of proper domineralizer operation on water with impurities is that the exiting water will ALi[&If have:

A.

lower conductivity.

B.

higher conductivity.

C.

lower pH.

.l D.

higher pH.

j QUESTION:

40 During maintenance activities, breakers in the open position are TAGGED and RACKED OUT to:

A.

deenergize components and associated control and indication circuits.

B.

provide administrative control where safety is not of prime importance.

C.

maintain remote indication of breaker position (where available) to ensure personnel safety.

D..

permit immediate availability of the breaker if required for emergency use.

BWR FORM A

l s

i BWR FORM A QUESTION: 41 Which of the following local breaker indications would provide the MOST ACCURATE information for determining the position of a 4160 volt feeder breaker?

i A.

Overcurrent trip flags and load side voltage B.

OPEN/ CLOSED mechanical flag indication and load side voltage C.

OPEN/ CLOSED indicating lights and load side current D.

Overcurrent trip flags and load side current QUESTION: 42 The function of high voltage electrical disconnects is to:

A.

isolate equipment electrically during no load conditions.

B.

isolate equipment electrically during overload conditions.

C.

protect circuits during overcurrent conditions.

D.

protect circuits during undervoltage conditions.

QUESTION: 43 Which of the following generator conditions is MOST LIKELY to cause generator damage because of high current?

A.

Tripping the output breaker under full load conditions

-B.

Tripping the generator prime mover under full-load conditions C.

Closing the output breaker on a bus that has an open circuit fault l

D.

Closing the output breaker on a bus that has a short circuit l

fault 1

I l'

BWR FORM A 16

+

o BWR FORM A QUESTION: 44 If a breaker is racked in/out to the ' test" position, the:

b A.

normal breaker opening and closing operations cannot be tested because the test position is for overload testing only.

B.

breaker can only be operated manually at the switchgear.

C.

remote position indication for the breaker is still operational.

D.

electrical jumpers must be connected to the operating coils to operate the breaker, i

QUESTION: 45 Delayed neutrons are neutrons that:

A.

have reached thermal equilibrium with the surrounding medium.

B.

are born within 10 14 seconds of the fission event.

C.

are born at the lowest average kinetic energy of all fission neutrons.

D.

are responsible for the majority of U 235 fissions.

QUESTION: 46 The interaction - in the reactor core that is MOST efficient in thermalizing neutrons for fission occurs with the:

A.

hydrogen atoms in the water molecules.

B.

oxygen atoms in the water molecules.

C.

boron atoms in the control rods.

D.

zirconium atoms in the fuel cladding.

BWR FORM A 17 i

I

BWR FORM A

{

QUESTION: 47

}

Which of the following conditions describes a reactor that is II&GILI critical?

)

A.

Keff - 1; delta K/K - 0 j

B.

Keff - 1; delta K/K - 1 I

Keff - 0; delta [K/K - 0 C

D.

Keff - 0; delta K/K - 1

[

QUESTION: 48 When determining shutdown margin for an operating reactor, how many control rod assemblies are assumed to remain FULLY withdrawn?

l A.

A single control rod of the highest reactivity worth B.

A symmetrical. pair of control rods of the highest reactivity worth C.

A single control rod of average reactivity worth D.

A symmetrical pair of control rods of average reactivity worth i

QUESTION: 49 During a reactor startup, the intermediate range monitor (IRM) readings go from 30 percent to 65 percent on the.same range in 2 minutes with no. operator action.

Which of the following is the average REACTOR PERIOD during the power increase?

A.

120 seconds B.

155 seconds C.

173 seconds D.

357 seconds 4

BWR FORM A 18 5

t BWR FORM A i

QUESTION:

50 Without delayed neutrons in the neutron cycle, when positive reactivity is added to a critical reactor, the reactor will:

(

A.

not be able to attain criticality.

.B.

begin an uncontrollable rapid power increase.

C.

experience a rapid but controllable power increase.

o

,D.

experience a prompt jump in power level followed by a decrease to the initial power level.

t QUESTION:

51 f

As the core ages, the amount of positive reactivity required to make the reactor prompt critical will because the effective delayed neutron fraction A.

increase; increases B.

increase; decreases l'

l C.

decrease; increeses D.

decrease; decreases L

4 QUESTION:

52 The moderator temperature coefficient describes a change in j

resulting from a change in l

A.

reactivity; moderator temperature l

B.

Keff; moderator temperature C.

moderator temperature; reactivity l

D.

moderator temperature; Keff BWR FORM A 19

n.

I, p ',

+

4 va T

( ',

?.

g BWR FORM A g

QUESTION:.53 1

)

During a hot reactor stcrtup with the reactor coolant at $20 degrees F, excessive

~'

rod withdrawal results in a 10 second reactor period.

Without any further operator; action,-the-coefficient will respond FIRST to reduce the -

rate'of'the power increase.

Ih A.

pressure B.

-void C.

moderator 1

[

D.

doppler L

I 1

QUESTION: :54 e

The reactor is operating at steady-state 50 percent power.

A control rod is inserted a short distance (from 08 to 02 notches). Assuming that recirculation L_

flow reacins constant,' reactor power will:

x A.

increase and stabilize at a higher value.

l

.B.-

increase temporarily, then return to the original value.

L_

i'

' C. ---

- decrease and stabilize at a lower value.

D..

decrease; temporarily, then return to the original.value.

1 1

-QUESTION:

55 I

Neutron flux shaping within a reactor core is designed to:

A.

minimize the effects of rod shadowing.

B.

- ensure that'more power is generated in the lower portion of the core.

h C.-

ensure that local core power limits are not exceeded.

L D..

minimize the effects of an ejected rod.

L l.-

BWR FORM A 20 4

j. -

i o

y;r.,I.

Y5hik[

w g,7

.s.

= '

en

..o BWR FORM A J

QUESTION:- $6 g

The 2EQ characteristics of Xe 135 that result in it' being a MAJOR reactor poison g1 Lis its relatively-

- half-life and relatively absorption cross y

section.

]

p-

.A.

short; large B.1

'short; small i

C.

.long; large k

D.

-long;.small i

QUESTION:

57 II The'H&22R contributor to the production of Xe 135 in a reactor operating at full

~

power is:-

A..

the radioactive decay of' iodine.

R L

B..

the radioactive decay of promethium.

I l'

C.

direct production from fission of U 235.

l l

l D.

direct production from fission of U 238.

1 l

l QUESTION:

58 The two methods of Xe-135 REMOVAL from a reactor operating at full power are:

i L

LA.

neutron scatter and beta decay.

l.

B.'

alpha decay and neutron absorption.

l C.

fission?and alpha decay.

D.

beta decay and neutron absorption.

l i

L

^

BWR FORM A 21 4

4 e-k

(

t y..

BWR FORM A-QUESTION: 59 Following a 2 week shutdown, a reactor is taken critical and ramped to full power in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.: How long will it take to achieve an equilibrium xenon condition after the reac' tor reaches full power?

6 A..

1 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s-

~B.

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

s C.

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

100 to 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />

-QUESTION: 60 i

I A rbactor has been operating at 25 percent power for 5 days when a scram occurs.

Xe-135 will PEAK in approximatelyt A,

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

B.

$ hours.

C.

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

20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

s L

r L

L-

-QUESTION:

61 A reactor has been operating at full power for several weeks when a scram occurs.

When the reactor is brought critical 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> later, Xe 135. concentration will

^be IWiHEU in' the

' of the core, which causes thermal flux - to be HIGHEST in.the. _

of the core.

A.

periphery; center L

. B.-

' periphery; periphery

([

C.

-center; center D.

center; periphery 1,

BWR FORM A 22

)

4

3 U-m~

e.:

g BWR FORM A QUESTION:- 62 Th's reactor is being started up'and taken.to rated power following.an extended h

-outage..

(Assume a-constant ramp rate.)

To compensate for the effect of l,

Xenon.135 while INCREASING reactor power, it will be necessary to rods:

l1 and recirculation j

flow.

1.

A.

withdraw; decrease B.

withdraw; increase C.

insert; increase l

l D.

insert; decrease l

L 1

. QUESTION:

63 A reactor has been operating at full. power for 10 weeks when a scram occurs.

1 Twenty four hours later, the reactor is brought critical and power level is maintained on range 5 of the intermediate range monitors. To maintain a CONSTANT power level.for the next several hours, control rods must be:

A, inserted, because the critical reactor will cause a high rate of xenon burnout.

'B.,

maintained at the present height as xenon establishes its equilibrium value for this power level.

J C.

inserted, because xenon will approximately follow its normal decay curve.

D.

. withdrawn, because xenon concentration is-increasing toward equilibrium.

. QUESTION:

64 f

Burnable poisons are loaded into the core to:

A.

allow the initial core to have excess reactivity to extend core life.

B.

allou shallow rods to compensate for core burnout.

C.

reduce the amount of time required for xenon to peak following a scram.

4 D.

provide for flux shaping in areas of deep rods.

BWR FORM A 23 l

I-

~

BWR F05G1 A.

QUESTION: 65

}

A reactor is operating at 100 percent power and flow. Reactor power is reduced by driving control rods in.

(Recirculating pump speed remains constant.) What is the effect on core flow?

A.

Core flow will increase, due to the decrease in two phase flow resistance.

B, Core flow will remain constant, because reactor power does not affect core flow.

C.

Core flow will decrease, due to an increase in two phase flow resistance.

D.

Core flow will decrease, due to the decrease in recirculation ratio.

QUESTION: 66 While withdrawing control rods during a reactor startup, the count rate doubles.

If the SAME amount of reactivity that caused the first doubling is added again, the count. rate will and crabilize at a higher level and the reactor will be A.

double; suberitical

. B.

double; critical l

C.

more than double; suberitical l

[

D.

more than double; critical QUESTION: -67 A reactor startup is in progress with Keff at 0.995 and stable source range indication.

If Keff is increased to 0.997 by control rod withdrawal,. reactor L

period will initially become and then 1

l A.

shorter; approach infinity B.

shorter; continue to gradually shorten I+

longer; approach infinity C.

D.-

longer; continue to gradually lengthen BWR FORM A 24

-I

g7:

By f

S-4 1,,. s

>g BWR' FORM A 1

- QUESTION:

68 With Keff - 0.985, how much reactivity must be added to make tNo reactor critical?-

A.-

1.324' delta-k/k' B.

1'.42% delta k/k

- C..

1.52% delta-k/k-

D.

1.62tl delta k/k-m t

QUESTION:

69 During a reactor startup, a stable positive 30 second reactor period is achieved with.no further reactivity addition. The reactor is:

A.

exactly critical.

B.

supercritical.

C.

suberitical.

D.

prompt critical.

i

- QUESTION:

70 Following a normal reactor shutdown,. steam production may continue for some '

s period of time, with the RATE of steam production dependent uponi ll (i

shutdown.

i A.

the : previous power' history of the plant and the time elapsed : since i

[

B.

.ths amount of time-required for the reactor power level to drop below the

' point of addin6 heat.

C.

.the reactor power level at the time of shutdown and initial - reactor -

pressure vessel water level.

D.

the recirculation flow rate and the pressure being maintained in the RCS.

l BWR FORM A 25 4

3

';r.-

t... ;

+ '

' I BWR' FORM A.

l-QUESTION:

71-u

- Upon reaching criticality during a reactor startup, the operator establishes a

- positive reactor period..Upon reaching the point of adding heat, the period will.

-becomeL due to the reactivity feedback of moderator and fuel, temperature.

A.'

shorter; negative

- B.

shorter; positive C.

-longer; negative 1

\\,-

~ Di

' longer; positive e;

. QUESTION:

72

~

During-a, normal: power increase from 20 percent to 100 percent,.the SMALLEST negative. reactivity addition is caused by the change in.

. A.'

fue1~ temperature.

i

- B.

moderator temperature.

C.

. xenon concentration.

L D..

void content.

4 i

+

i 1

.t

\\

BWR FORM A 26 A

L

>1 4.

cp.p 0-BWR FORM A p

QUESTION:

73.

Refer to the figure.below for the following question, o

t; ~-

-- A differential pressure manometer filled with water is installed 'across' an orifice in a-ventilation duct to determine the direction of airflow. With the ventilation conditions as shown,'the pressure at P1 is than P2, and airflow is A.

' greater; left to right a

B.

- greater; right to left C.

less; left to right D.

less; right to left I

5 f//////////////

l W

P P

g 2

'///

'//////>

l l-1.

y QUESTION:

74 l

[

. Which one of the following has the LOWEST quality?

A'. - Superheated steam B. lSubcooled liquid i

f

. C.

Saturated steam D.

. Saturated liquid 9

DWR FORM A 27

7,

/1 4

.'h

g. +

+

-BWR FORM A r

QUESTION:

75' 1

L

_ The saturation pressure.for. water-at 328 degrees F.is:

i A.

-85'psig.

- B.

.100 psig.

' C.

115 psig.

D.-

130 psig.

s-QUESTION: 76 L

During jet pump operation, Ja high pressure, low velocity fluid flow is supplied-through' a where -the pressure drops and the velocity increases,

' creating a low pressure area in the _

section.

A.

nozzle; throat

- B.-

nozzle; diffuser C.

' diffuser; th'roat-1.

- D.

diffuser; nozzle i

~

p o

l

-QUESTION:

77-l'

\\

I.

Condenser pressure is 1.0 psia.

During the cooling process in the condenser, l'

the LP turbine exhaust reaches a-temperature of 101~ degrees F,_at which time it

. is a:

i-

- i l

A.

saturated' liquid.

1:

B; saturated vapor.

j C.

subcooled liquid.

.- D.

.superheated vapor.

e BWR FORM A 28

[

t f

r

s.g g

t jp,c m.-c 1 :

. -e-BWR FORM A

. QUESTION:

78-y Uhich of the 'following is th'e MOST PROBABLE steam plant location-for superheated

+

steam?1

'A.

The outlet of the high' pressure turbine li ~ B.

The-outlet'of the moisture separators / reheaters

; ib H

As " fluid-flow - rate INCREASES-through the tubes of a shell-and-tube ~ heat --

excha'nger, the laminar film thickness which causes-heat transfer i

1 L4 rate.to A.~

increases;, increase

' B'.

increases; decrease-

'C.

decreases; increase.

'DJ decreases; decrease i

ti i

BWR FORM A 31

)

{!

s.

1

- o,

's 1

BWR FORM A QUESTION: l87 Departure from nucleate boiling (DNB) occurs when steam bubbles begin to blanket

~

4 3

the: fuel rod, resulting in a rapid in heat transfer rate and a rapid in delta.T (fuel rod minus coolant temperature).

A' decrease; increase B.

decrease; decrease

- C.

increase; increase k

- D.

increase; decrease b

\\s t

1 BWR FORM A

'32 4

,1

,w

.g' t.

i

.e-A.

BWR. FORM A x

- QUESTION:

88 l

Refer to-the figure below for the ' following question.

l

~

TFor the hypothetical fuel coolant channel shown below, identify along its length.

p.

4 -

. where TRANSITION BOILING begins.

L_.

+

J.

A.

1

. B..

.2 5

?

C.

3

.i

y

.y

.D.-

'4-

• • l*

f.

% 4-l' 1

It i

e.*,*

• 3

,1,*..* I.1

~

?

e I

r r

.}[

$Y.

F)e a

C.'

n y

2

- DIRECTION I

OF Flow f

h i

b

=-- 1

=

a'

.. g.

Channel BWR FORM A 33

.1-

\\

q

< g.,

-j

'y w

1 BWR FORM A i

~,

s e

J

-QUESTION:,

Refer to the figure below for tho' following question.

~

On the figure of a pool boiling curve', the point at which heat flux is increasing

.and the critical heat flux has been reached (point B), marks the onset of:

t-1

^

A.

single-phase convection.

j B.

film boiling.

C.- nucleate boiling, j

D,' partial film boiling.

j i

f I

l

/

i

.l 1

l 4

l6 3

l I

I l-1 I

I I

i I

a i

l l

D o

Hem phs i

l I

l i

I g

1 g

1 I

I I

I i

i 1

1.

.I I

I i

i l

I l

l l

1 I

l l

I i

l' l!

I l

I Log AT BWR FORM A 34 i

h i

6

l d

y w

s

.(

BWR FORM A

]

-QUESTION:' 90 n

Void fraction-is the ratio.of the-of steaa - to the -

of steam / water mixture at. a given elevation in the, fuel coolant channel.

A.

volume; mass-1 B.

mass; mass i

C.

volume; volume D.

massi volume

!i 1

i QUESTION:

91' Core orificing is used in the reactor core because the orifices:

A.

counteract the buoyant force of the bubbles accelerating flow in the high-i

-powered bundles.

-B.'

improve the distribution of core flow to offset the effect of incressing quality on bundle flow.

C.

increase core delta P so that minor crud buildup on fuel bundles will not adversely. affect flow.

D.

decrease ~ flow during periods of natural circulation to increase the void coefficient.

-i L

QUESTION: 92 1'

l' The reactor is at 100 percent power when a ' trip of the recirculation pumps L

occurs. Void fraction percentage will:

l

.A.

stay the same due to minimal changes in reactor pressure.

B.

decrease because steam bubbles are no longer being generated.

C.

increase because steam bubbles are no longer being swept _away.

D.

decrease initially due to reactor pressure increase, then return to initial value.

l l-BWR FORM A 35 s,,

\\

e-L

.L

3. '

7

-BWR FORM A QUESTION:' 93

[

With the reactor shutdown and the reactor recirculating pumps isolated, it is important to monitor reactor vessel SKIN TEMPERATURES because:

A.

cooldown rates are easily exceeded with the recirculation pumps isolated.

B.

these temperatures will provide one of the first indications of thermal' stratification.

C.

these temperatures are the only reliable source of reactor recirculation I

loop temperature.

D.

these temperatures must be maintained constant with no flow in the core.

QUESTION:

94 P

Which one of the following pararieter changes will cause an INCREASE in the critical power of a fuel bundle?

-A.

The subcooling of the coolant entering the bundle decreases.

B.

The local peaking factor increases.

'C.

The coolant flow through the bundle increases, i'

D.

The axial power peak shifts from the bottom to the top of the bundle.

l-i QUESTION:

95 Operatin5 the reactor below the linear heat generation cate (LHGR) thermal limit prevents:

l A.

cracking of the fuel cladding due to high stress from fuel pellet i

l

' expansion.

B.

melting of the fuel cladding due to a cladding temperature exceeding 2,200 degrees F during an anticipated transient without a scram (ATWS).

C, cracking of the fuel cladding due to the lack of cooling caused by departure from nucleate boiling.

D.

gross -fuel cladding failure due to a lack of cooling following a loss of coolant accident (LOCA).

BWR FORM A 36

.i l

il Xs t-.

. ' ~.

.BWR FORM A QUESTION:' 96 Icy Maximum fraction of limiting power density (MFLPD) is defined as and must be maintained

[MGR is the linear heat generation ra ;.j A.

MGR actual /MGR limit;' <1

- B.

MGR actual /MGR limit; >l C.

LHGR limit /MGR actual; <1

,D. MGR limit /MGR actual; >l c

QUESTION:

97 The amount of heat stored in tho ' fuel, resulting from the operating ' KW/f t N

existing in the fuel. PRIOR to a scram, describes the:

A.

average planar linear heat generation rate - (APMGR).

h i

B.

maximum average planar linear heat generation rate (MAPMGR),

C.

preconditioning interim operating management: recommendations-(PCIOMR).

D.

maximum average planar linear heat generation rate limit (MAPRAT).

QUESTION:

98 Which one of the following expressions describes the critical power. ratio?

i. A.

Actual ~ bundle power /criti. cal power.

B.

Critical power / actual bundle power C.

Average bundle power / critical power I

D.

Critical power / average bundle power x.

BWR FORM A 37

.c>

+

i m.

E.

r g

t.

h.

n.. -

BWR FORM A L.

-QUESTION:- 99.

Which of the following describes the effect of fast neutron irradiation on a f

. reactor pressure vessel (RPV)?

A.

Increased fatigue crack growth rate B.

Decreased stress which must be applied to the RPV, to cause plastic l

deformation I

C.

Increased ductility D.-

Increased nil ductility reference transitior, temperature QUESTION:

100 A COMPRESSIVE stress will be applied to the OllTSIDE wall of the reactor vessel as a result of:

A.

neutroni embrittlement of the reactor vessel.

B.

increasing RCS pressure.

'C.

performing an R,CS cooldown.

D.

performing an RCS heatup.

b e

BWR FORM A 38

Yv f

? ' j s.'

,e>

,1 ',1 3 -

.e ENCIDSURE 2

.k

";,w E

GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES)

BOILING WATER REACTOR FORM B t

=

5 l

l ENCLOSURE 2

t 5, _,j

.,=.

FEBRUARY 1990 BWR GFE - FORM B-ANSWER KEY 11.

' C:-

26.

A 51.

A 76.

C 4

2.

A 27.

C 52.

A 77.

B-3.

A 28.

B 53.

A 78.

D i

-4.

A 29.

A-54.

B 79.

D 5.-

B 30.

DELETED 55.

D 80.

D p

6.

B 31.

A 56.

C 81.

A 7.-

D 32.

A 57.

DELETED 82.

A'

f 8.

A 33.

C 58.

A 83.

C 9.

D 34.

B 59.

C 84.

B 110.

C 35.

C 60.

A 85.

A i

L 11.

DELETED 36.

B

61. - B 86.

D 12.

C 37.

B 62.

C 87.

B 13.

-A 38.

A 63.

A 88.

D 14.

D 39.

B 64.

D 89.

C 15.

C 40.

B 65.

C 90.

A 16.

B 41.

D 66.

A

91. -

B

.17.

D 42.

C 67.

C 92.

C 18.

B 43.

A 68.

A 93.

D R19.

C

-44.

C 69.

B 94.

A 20.

A 45.

D 70.

C 95.

A 21.

A 46.

C 71.

B 96.

B 22.-

D 47.

B 72.

C 97.

A 23.

.A 48.

-C.

73.

A 98.

D

- 24.

C o49.

B 74.

A-L99.

D 25.-

B 50.

C 75.

D 100.-

C i

v.,

s' 4

'4 1

BWR FORM B RULES AND GUIDELINES FOR THE GENERIC FUNDAMENTALS EXAMINATION During the l administration of this examination the following rules.

apply:

(1)

-Print your name in the blank provided on the cover sheet of the examination.

(2)

-Fill in the'name of your facility.

(3)

Fill in the ID Number you were given at registration.

(4)

Fill in your start and stop times at the appropriate time.

(5)

Three handouts are provided for your use' during the examination, an i

Equations and Conversions sheet, instructions for filling out the answer sheet, and Steam Table booklets.

(6)

Use only the answer sheet provided. Credit will only be given for answers properly marked on this sheet. Follow the instructions for filling out the answer sheet.

L

'(7)

Scrap paper will be provided for calculations, l

(8)

Any questions about'an item on the examination should be directed to the examiner only.

(9)

Cheating on the examination will result in the automatic forfeiture of-l l~

this examination. Cheating could also result in severe penalties.

l (10) Restroom trips are limited. Only ONE examinee may leave the room at a-time.

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

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

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

(13) After turning in your examination materials,. leave the examination area, L

as defined by the examiner. If after leaving you are found in the l'

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

BWR FORM B

I

\\

/

.i EQUATION S H E E T.

j Net Work (out)

- $ : - a c - AT Cycle Efficiency - Energy (in) 1 p

'S/(1 - K rt)

-- $ Ah SCR I

CR (1 - K rs):

CR (1 - K.f t)1 2

k 2

' UA AT CRg/CRo 1/(1 - K.gg)-

M SUR - 26,06/r (I

• Erf t)0

-26.06 (Aert t.1 (1

K gg)g M

8'A *

(p.. p).

SN SDM' = (1 - K gg)/K gg Po 10 P

Wg a N'E Pwr P

- Po e 2*/(p*k) i:

(f*/p) + [(i - p)/A.gsp}

f I

r 1 x 10'8 ~ seconds f*

(K,gg. 1)/K,gg p

u AK.tr/K.cc '

A.tr - 0.1 seconds 1 lf

.p i --

2.21 lba L

1 Curie' - 3.7 x 1010 dps 1 kg 3.41 x 10' BTU /hr-1 hp

~

2.54 x 103 BTU /hr 1 Mw l-9/5 *C + 32 778 ft-lbf

'F 1 BTU 5/9 (*F

32)

L'

'c o

-q_ :

m BWR FORM B QUESTION:

1

~

4 Delayed neutrons are neutrons that:-

-A.

.have reached thermal equilibrium with the surrounding medium.

B.'.

are born within-10 14 seconds of the fission event.

C.

are born at the lowest average kinetic energy of all fission neutrons.

D.

are responsible for the majority of U 235 fissions.

QUESTION:

2

'The interaction in the reactor core that is MOST efficient in thermalizing neutrons for fission occurs with the:

A.

hydrogen atoms in the water molecules.

1 B.

oxygen atoms in the water molecules.

C.

boron atoms in the control rods.

D.

zirconium atoms in the fuel cladding.

QUESTION:

3 Which of the following conditions describes.a reactor that is EKACTLY critical?

A.

Keff - 1; delta K/K - 0 B.

Keff - 1; delta K/K - l' C

Keff - 0; delta-K/K - 0 D.

Keff - 0; delta K/K - 1 j

BWR FORM B 1

l.

p

~

1 BWR FORM B QUESTION:

4:

When determining shutdown margin for an operating reactor, how many control rod assemblies are assumed to remain FULLY withdrawn?

?

A.

A single ~ control rod of the highest reactivity,vorth B.

A symmetrical pair of control rods of the highest reactivity-worth-

-C.

A single control rod of average reactivity worth D.

'A-symmetrical pair of control rods of average reactivity worth QUESTION:

5 During a reactor startup, the intermediate range monitor-(IRM) readings go-

-from 30 percent to 65 percent on the same range in 2 minutes with no operator.

action. Which of the following is the average REACTOR PERIOD'during the power increase?

p A.

120 seconds B.

155 seconds C.

173 seconds sc l

-D.

357 seconds r

o

-QUESTION:

6 Without delayed neutrons in the neutron cycle, when positive reactivity is

~

.added to a critical reactor, the reactor will:

I A..

not be able to attain criticality.

1 B.

begin an uncontrollable rapid power increase.

C.

experience a rapid but cantrollable power increase.

D..

experience a prompt jump in power level followed by a decrease to the

' initial power level.

[

BWR FORM B 2

1

l e.-

i' 1

BWR FORM B QUESTION:

7 As theLcore ages,-the amount of positive reactivity required to make.the reactor prompt critical will because the effective delayed neutron fraction-A.

increase;. increases

-B.

increase; decreases C..

decrease; increases D.

decrease; decreases QUESTION:

8' The moderator temperature coefficient describes a change in resulting from a change in A.<

reactivity; moderator cesperature 1

L

'B.

Keff;-' moderator temperature

,l l

C.

-moderator temperature; reactivity D.,

moderator temperature; Keff l

l L

1

. QUESTION:

9 l

l j

l During a hot reactor startup with the reactor coolant at 520 degrees F.

L excessivt rod withdrawal results in a.10 second reactor period.- Without any

),~

further operator action, the coefficient will respond FIRST to-reduce the rate of the power increase, i

r A.-

pressure 1-D B.

void

[.

C.

moderator l

D.

~ doppler 1

l' l

1$

i BWR FORM B 3

1 g.

B-i

BWR FORM B QUESTION:

10

-The reactor is operating at steady state 50 percent power. A control rod is inserted a short distance (from 08 to 02 notches)'. Assuming that recirculation' flow remains constant, reactor power will:

A.

increase and stabilize at a higher value.

B.

increase' temporarily, then return to the original value.

C.

decrease and stabilize at a lower value.

D.

decrease temporarily then return to the original value.

QUESTION:

11 Neutron flux shaping within a reactor core is designed to:

A.

minimize the effects of rod shadowing.

u l

B.

ensure that more power is generated in the lower portion of the core.

C.

ensure that local core power limits are not exceeded.

\\

D.

minimize the effects of an ejected rod.

QUESTION:

12 The IEQ characteristics of Xe-135 that result in it being a MAJOR reactor i

poison is its relatively half life and relatively. __

l absorption cross section.

-A.

short; large B.

short;-small C.

long; large D.

long; small BWR FORM B-4

's?

1

lll*!

e BWR FORM B i

a

QUESTION

13L t-j The MAJOR contributor ' to the production of Xe 135 in-a reactor operating at

full power is:

i A.

-the. radioactive decay _of iodine, i

B '.

the radioactive decay of promethium.

C.

direct' production from fission of U-235.

D.

direct production from fission of U 238.

QUESTION: 14 The two methods of Xe 135 REMOVAL from a reactor operating at full power are:

A.

~ neutron scatter and beta decay.

B.__

alphafdecay and neutron absorption.

C.

fission.and alpha. decay.

)

D.

beta decay and neutron absorption.

I q

QUESTIONE 15-Following a.2 week shutdown, a reactor is-taken critical and ramped to full power in-6 hours. How long will it take to achieve an, equilibrium xenon condition after the_ reactor reaches full power?

A.

-1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> I

B.

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

40 to 50. hours-D.

100 to 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> BWR FORM B 5

t m.

i i

J

=e g

BWR FORM B i

QUESTION:

16 A reactor has been operating at 25 percent power for 5 days when a scram occurs. -Xe.135 will PEAR in spproximately:

j y

A.

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

I B.

$ hours.

C.

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

D.

20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

l i

QUESTION:

17 I

A reactor has been operating at full power for several weeks when a scram r

k' hen the reactor is brought critical 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> later, Xe 135 occurs.

concentration will be HICREST in the of the core, which causes thermal flux to be HIGHEST in the of the core.

j

-A.

periphery; center 3r q

B.

periphery; periphery j

i C.

center; center

(

D.

center; periphery i

i QUESTION:

18 The retetor.is being started up and taken to rated power following an extended L

outage.

(Assume a constant ramp rate.) To compensate for the effect of-l' Xenon 135 while INCREASING reactor power, it will be necessary to __

rods and recirculation flow.

A..

withdraw; decrease B.

withdraw; increase C.

insert; increase D.

insert; decrease BWR FORM B 6

g-

--,g

+

BWR F030( B QUESTION:

19 A reactor has been operating at full power for 10 weeks when a scram occurs.

Twenty four hours later, the rr. actor is brought critical and power level is maintained on range 5 of the intermediate range monitors.

To maintain a CONSTANT power level for the next several hours, control rods must be:

A, inserted, because the critical reactor will cause a high rate of xenon burnout.

B.

maintained at the present height as xenon establishes its equilibrium value for this power level.

C.

inserted, because xenon will approximately follow its normal decay curve.

D.

withdrawn, because xenon concentration is increasing toward equilibrium.

QUESTION:

20 Burnable poisons are loaded into the core to:

A.

allow the initial core to have excess reactivity to extend core life.

B.

allow shallow rods to compensate for core burnout.

C.

reduce the amount of time required for xenon to peak following a scram.

D.

provide for flux shaping in areas of deep rods.

L l

l l.

l~

1 l

BWR FORM B 7

l-L

4' BWR FOIGt B QUESTION:

21 A reactor is operating at 100 percent power and flow. Reactor power is reduced by driving control rods in.

(Recirculating pump speed remains constant.) What is the effect on core flow?

A.

Core flow will increase, due to the decrease in two. phase flow resistance.

B.

Core flow will remain constant, because reactor power does not affect core flow.

C.

Core flow will decrease, due to an increase in two phase flow resistance.

D.

Core flow will decrease, due to the decrease in recirculation ratio.

QUESTION:

22 While withdrawing control rods during a reactor startup, the count rate doubles.

If the SAME amount of reactivity that caused the first doubling is added again, the count rate will and stabilize at a higher level and the reactor will be A.

double; suberitical B.

double; critical C.

more than double; suberitical D.

more than double; critical QUESTION:

23 A reactor startup is in pregress with Keff at 0.995 and stable source range indication.

If Keff is increased to 0.997 by control rod withdrawal, reactor period will initially become and then I

A.

shorter; approach infinity B.

shorter; continue to gradually shorten C.

longer; approach infinity D.

longer; continue to gradually lengthen BWR FORM 3 8

BWR FORM 3 QUESTION:

24 With Keff. 0.985, how much reactivity must be added to make.the reactor E

critical?

A.

1.326 delta k/k B.

1.426 delta k/k C.

1.52% delta k/k i

D.

1.62% delta.k/k i

i QUESTION:

25 i

During a reactor startup, a stable positive 30 second reactor period is i

achieved with no further reactivity addition. The reactor is:

r A.

exactly critical.

B.

supercritical, C.

suberitical.

D.

prompt critical.

I QUESTION:

26 i

Following a normal reactor shutdown, steam production may continue for some period of time, with the RATE of steam production dependent upon:

A, the previous power history of the plant and the time elapsed since t

shutdown.

l B.

the amount of time required for the reactor power level to drop below the point of adding heat.

L C,

the reactor power level at the time of shutdown and initial reactor pressure vessel water level.

D.

the recirculation flow rate and the pressure being maintained in the RCS.

1 SWR FORM B 9

l.

f

.------u e

P W,

c BWR FORM B QUESTION 27.

Upon reaching criticality during a reactor startup, the operator establishes a positive reactor period. Upon reaching the point of adding heat, the period will become due to the reactivity feedback of moderator and_ fuel temperature.

[

~A.

shorter; negative i--

B.

shorter; positive l-C.

longer; negative

-D.

longer; positive QUESTION:

28 During a normal power increase from 20 percent to 100 percent, the SMALLEST negative reactivity addition is caused by the change in:

A.

fuel temperature.

B.

moderator temperature.

C.

xenon concentration.

D.

void' content.

BWR FORM B 10

4 j

BR FORM k QUESTION:

29.

Refer to the figure below for the following question.

A differential pressure nanometer filled with water is installed across an orifice in a ventilation duct to determine the direction of airflow. With the ventilation conditions as shown, the pressure at P1 is than P2, and

. airflow is h-A.

greater; left to right B.

greater; right to left C.

less; left to right D.

less; right to left i

///////////////

w 1

S i

m

'///

'//////>

l

?

I 1'

l BWR FORM B 11

p -.

I r

BWR FORM B f

l QUESTION: 30 i

Which one of the following has the lhWEST quality?

A.

Superheated steam r

j i

B.

Subcooled liquid r

C.

Saturated steam t

D.

Saturated liquid

[

t QUESTION:

$1 i

r The saturation pressure for water at 328 degrees F is:

[

A.

85 psig.

8, 100 psig.

i C.

115 psig.

D.

130 psig.

QUESTION:

32 During jet pump operation, a high pressure, low velocity fluid flow is supplied through'a where the pressure drops and the velocity increases, creating a low pressure area in the _

section.

A.

nozzle; throat B.

nozzle; diffuser C.

diffuser; throat i

D.

diffuser; nozzle BWR FORM B 12 1

~

'e'

o.

agg yonn B QUESTION:

33 Condenser pressure is 1.0 psia. During the cooling process in the condenser, the LP turbine exhaust reaches a temperature of 101 degrees F, at which time it is a:

A.

saturated liquid.

B.

saturated vapor.

C.

subcooled liquid.

D.

superheated vapor.

QUESTION: ~34 Which of the following is the MOST. PROBABLE steam plant location for superheated steam?

A.

.The outlet of the high pressure turbine

-B.

The outlet.of the moisture separators / reheaters C.

The inlet of the high pressure turbine D.

The outlet of the low pressure turbine I,

QUESTION:

35 A sudden stop of fluid flow in a piping system, due to rapid closure of an l

isolation valve, will MOST LIKELY result in:

L A.

check valve slamming.

l-B.

pump runout.

l C.

water hammer.

l D.

pressurized thermal shock.

I l

BWR FORM B 13 i

e BWR FORM B QUESTION:

36 i

s Cavitation'is the formation of vapor bubbles in the pressure area of a pump followed by the of these bubbles within the pump casing.

A.

Iow; expansion B.

Iow; collapse C.

high; expansion r

D.

high; collapse QUESTION: 37 The available net positive suction head (NPSH) of a centrifugal pump:

A.

decreases with increased subcooling to the pump.

B.

decreases with an increase in pump flow rate.

C.

increases as the suction temperature increases.

D.

decreases as pump discharge pressure increases.

QUESTION:

38 A centrifugal pump 1. being returned to service after maintenance. The operator FAILS to v.ot the pump properly. When the pump is started the operator should see capacity and discharge head.

A.

lover; lower l

B.

lower; higher C.

higher;-lower 1

L D.

higher; higher l

1 l

BWR FORM B 14 ax.

I o

e 4

o

s.

BWR FORM B i

QUESTION:

39 t-The H&l2B effect of operating centrifugal pumps in PARALLEL is:

i A.

increased system pressure.

i i

g B.

increased system flow rate.

I t

i C.

decreased system pressure.

i 1

1 D.

decreased system flow rate.

I l-

]

1 i

f

i..

QUESTION: 40 j'

A common method used in emergency cooling water systems to REDUCE the flow rate lost from a pipe rupture, thereby EHEERIH2 design cooling flow capability..is the installation of:

A.

venturis B.

orifices C.

redundant pumps D.

pipe hangers 1

QUESTION: 41

- The heat transfer mechanism that accounts for the MAJORITY of core heat removal during a LOCA after total core voiding is:

A.

conduction.

B.

convection.

C.

radiolysis.

D.

radiation.

l l

BWR FORM B 15 i

r 1

t l-s'

'e BWR FOM B

-QUESTION:

42 i

i As fluid flow rate INCREASES through the tubes of a shell and. tube heat exchanger, the laminar film thickness

, which causes heat transfer rate to 6

A.

increases; increase i

B.

increases; decrease l

C.

decreases; increase i

D..

decreases; decrease s

1 i

QUESTION: 43 i

Departure from nucleate boilin6 (DNB) occurs when steam bubbles begin to blanket the fuel rod, resulting in a rapid _

in heat transfer rate and a rapid in delta.T (fuel rod minus coolant temperature).

~

A.

decrease; increase 3.

decresse; decre..ase 8j C.

increase; increase D.

increase; decrease h

7 i

b

'. F

't i

y 1'

L.-

B arR F O M B 16 l

l l

1

%'A

~.

f l

BWR FOM B p

QUESTION: 44 i

g

- Refer to the figure below for the following question.

For the hypothetical fuel coolant channel shown below, identify along its l.tngth where TRANSITION BOILING begins.

A.

1 B.

2 I

+

C.

3 D.

4 r

it

'.'. :*,..j :,.

l e--- 3 f.::: 4 (l

\\

?

IN i

1 l

>b Y

I i

i f

T.

4, g

DIRECTION I

OF Flow p-l..

.- - 1 R

nw l'

chaarel i.

1 l-i BTR FOM B 17 Y%

-v.

]

it j

>+

c i:

BWR FORM B l

J

^

QUESTION: 45 j

t Refer to the figure below for the following question.

On the figure of a pool boiling curve, the point at which heat flux is-increasing and the critical heat flux has been reached (point B), marks the onset of:

i A.

single. phase convection, i

B.

film boiling, C.

. nucleate boiling.

D.

partial film boiling.

I I

j i

l l6 l

l l

l I

l l

1 t

.11 I

a 1

l i

i i

I l

i I

I I

I I

i l

l i

~

~

1 I

I I

l I

1 i

1 i

~,

i i

i!

i i

i i

Log AT 4

6 BWR FORM B 18 e

w 09 5

h s

BWR FOIQi 3 QUESTION:

46 Void fraction is the ratio of the of steam to the of steam / water mixture at a given elevation in the fuel coolant channel.

A.

volume; mass B.

mass; mass C.

volume; volume D.

mass; volume QUESTION: 47 Core orificing is used in the reactor core because the orifices:

A.

counteract the buoyant force of the bubbles accelerating flow in the high-powered bundles.

B.

improve the distribution of core flow to offset the effect of increasing quality on bundle flow.

C.

increase core delta P so that minor crud buildup lon fuel bundles will not adversely affect flow.

D.

decrease flow during periods of natural circulation to increase the void coefficient.

QUESTION:

48 The reactor is at 100 percent power when a trip of the recirculation pumps occurs. Void fraction percentage will:

A.

stay the same due to minimal changes in reactor pressure.

B.

decrease because steam bubbles are no longer being generated.

C.

increase because steam bubbles are no longer being swept away.

D.

decrease initially due to reactor pressure increase, then return to initial value.

BWR FORM B 19

i e

BWR FORM B QUESTION:

49.

With the reactor shutdown and the reactor recirculating pumps isolated, it is important to monitor reactor vessel SKIN IEMPERATURES because:

A.

cooldown rates are easily exceeded with the recirculation pumps isolated.

B.

these temperatures will provide one of the first indications of thermal stratification, t

C.

these temperatures are the only reliable source of reactor recirculation loop temperature.

D.

these temperatures must be maintained constant with no flow in the core.

QUESTION:

50 Which one of the following parameter changes will cause an INCREASE in the critical power of a fuel bundle?

A.

The subecoling of the coolant entering the bundle decreases.

B.

The local peaking factor increases.

C.

The coolant flow through the bundle increases.

D.

The axial power peak shifts from the bottom to the top of the bundle, QUESTION:

51 Operating the reactor below the linear heat generation rate (LHGR) thermal limit prevents:

A.

cracking of the fuel cladding due to high stress from fuel pellet expansion.

B.

melting of the fuel cladding due to a cladding temperature exceeding 2 200 degrees F during an anticipated transient without a scram (ATWS).

C.

cracking of the fuel cladding due to the lack of cooling caused by departure from nucleate boiling.

D.

gross fuel cladding failure due to a lack of cooling following a loss of coolant accident (LOCA).

BWR FORM B 20

i

.I

BWR FORM 3 QUESTION:

$2 Maximum fraction of limiting power density (MFLPD) is defined as and must be maintained

[LHGR is the linear heat generation rate.)

A.

LHGR actual /LHCR limit; <1

\\

B.

LHCR actual /LHGR limit; >l I

C.

LHCR limit /LHCR actual; <1 D.

LHCR limit /LHCR actual; >l QUESTION:

53 The amount'of heat stored in the fuel, resulting from the operating KW/ft existing in the fuel PRIOR to a scram, describes the:

A.

average planar linear heat generation rate (APLHCR).

B.

caximum average planar linear heat generation rate (MAPLNGR).

'f C.

preconditioning interim operating management recommendations (PCIOMR).

D.

maximum average planar-linear heat generation rate limit (MAPRAT).

?

QUESTION:

54 Which one of the following expressions describes the critical power ratio?

[

A.

Actual bundle power / critical power

~!

B.

Critical power / actual bundle power C.

Average bundle power / critical power D.

Critical power / average bundle power BWR FORM B 21

\\

V,w e

i BWR FORM B i

QUESTION:

55 L

Which of the following describes the effect of fast neutron irradiation on a reactor pressure vessel (RPV)?

i A.

Increased fatigue crack growth rate i

B.

Decreased stress which must be applied to the RPV to cause plastic l

deformation C.

Increased ductility L

D.

Increased nil ductility reference transition temperature b

QUESTION:

56 i

A COMPRESSIVE stress will be applied to the OUTSIDE wall of the reactor vessel as a result of:

+

(

A.

neutron embrittlement of the reactor vessel.

B.

' increasing RCS pressure.

C.

performing an RCS cooldown.

l D.

performing an RCS heatup.

i

' QUESTION:

57 Which of the following statements describes the operation of reactor pressure vessel safety valves?

A.

When the activating pressure for a safety valve returns to the lift setpoint.

combination of air and steam pressure closes the valve.

B.

As reactor pressure increases to the lift setpoint, the pressure overcomes spring tension on the valve operator, causing the valve to fully open.

C.

As the disk on a safety valve lifts, less pressure is exerted on the disk, reducing the upward force on the disk, and thereby regulating the valve position.

D.

When the safety valve lift setpoint is reached, a pilot valve opens allowing reactor pressure to fully open the main valve disk.

BWR FORM B 22 a

p BWR FORM B QUESTION: 58 If a pressure control valve at the outlet of a heat exchanger is opened, system flow rate will and head loss will A.

increase; decrease B.

increase; increase C.

decrease; decrease D.

decrease; increase QUESTION:

59 All of the following are acceptable methods for verifying the position of a

-SHUT manual gate valve, EXCEPT:

J A.

observing the position of the valve stem using handwheel or position indicators.

B.

observing indicators for plant parameters, such as temperature, pressure and level.

C.

attempting to turn the handwheel in the "open" directier..

D.-

attempting to turn the handwheel in the " closed" direction.

I QUESTION:

60 The manual declutch lever of a motor operated valve the motor and-

,__ the handwheel.

[

A.

disengages; engages B.

doenergizes; engages i

C.

engages; disengages D.-

reenergizes; disengages BWR FORM B 23 i

4

iE 4

BWR.IhDRM B QUESTION: 61 Check valves are used to:

A.

relieve system overpressure, thereby ensuring system integrity.

B.

prevent backflow through non operating components or flowpaths.

C.

maintain a constant backpressure to control flow rate.

D.

prevent pump cavitation by keeping systems full of liquid.

QUESTION:

62 Operators should use 12IH hands on valve handwheels when positioning manual valves to:

A.

overcome the resistance of installed locking devices.

B.

control the rate of valve motion to prevent water hammer.

C.

ensure system pressure, temperature, and flow are controlled during valve motion.

D.

control lateral force to prevent bending the valve stem.

QUESTION:

63 Which one of the following failures of a wet reference leg differential pressure (D/P) level transmitter will cause its level indicator to indicate the LREERI level?

l A.

The D/p cell diaphragm ruptures.

B.

The reference leg ruptures.

C.

The variable leg ruptures.

l D.

The equalizing lina. ruptures, 1

BWR FORM B 24 i

1:

i

• =

BWR FORM B QUESTION:

64 If a resistance temperature detector (RTD) develops an QZZE circuit (bridge circuit remains intact), indication will fail:

o A.

high.

p B.

low.

C.

as is, h

D..

to mid scale.

l l.

l-l QUESTION:

65 A differential pressure level transmitter with its reference leg vented to atmosphere is being used in a control loop to maintain liquid level in a vented tank at 50 percent. The transmitter was calibrated at a tank temperature of 200 degrees F.

If the tank temperature gradually falls to 100 degrees F, the control loop will cause ACTUAL level to:

A.-

be maintained at 50 percent.

B.

increase and remain above 50 percent.

C.

first increase, then decrease to 50 percent.

D.

decrease and remain below 50 percent.

QUESTION:

66-A simple bellows pressure detector is located in the rect.1.or containment with its low pressure side vented to the containment.

If a Ltdn steam break raises containment pressure by 40 psig, the associated pressure indication (disregarding any temperature effect on the bellows) will:

A..

increase by the square root of 40 psig.

.1 B '.

increase by 40 psig, C.

decrease by 40 psig.

'D.

stay constant.

BWR FORM B 25 m

+-

BWR FO>IQi B o

i i

QUESTION:

67 b

A differential pressure (D/P) cell is being used to measure flow rate in a cooling water system, flow rate is indicating 75 percent of scale.

If the D/P cell diaphram ruptures, INDICATED flow rate will:

A.

-go to O percent.

B.

go to 100 percent (full-scale).

C.

remain the same.

1 D.

. move slowly to 50 percent (mid scale).

.A j

OUESTION:

68 A bourdon tube pressure detector that is indicating 50 percent of scale is.

suddenly exposed to a-pressure transient that extends the detector 75 percent l

l beyond its upper range value. Actual pressure returns to its original value.

' Assuming the detector remains intact, the affected pressure indication will I

initially go off scale high, and then:

A.

become unpredictable until the instrument is calibrated, j

B.

return to a pressure less than ori inal pressure, l

G C.

return to original pressure, L

,'I l

D.

return to a pressure greater than original pressure, l

i QUESTION:

69 1

Most of the electrons collected in a fission chamber are released as a result of ionizations caused DIRECTLY by:

J A.

fission fragments.

B.

fission Sammas.

C.

fission betas, l

(t D.

fissionable materials.

L o

{

1' l

BWR FORM B 26

--.- ---~.--.- -- -- --- --- ------- -

BWR F010( B

-QUESTION:

70 Which of the following statements describes the use of a self reading pocket dosimeter (SRPD)?

A.

SRPDs hold their charge indefinitely when removed from a radiation field.

B.

SRPD readings must be considered inaccurate when they are dropped.

C.

SRPDs can be used to record beta and gamma radiation.

D,

.The output of an SRPD is a dose rate in ar/hr.

QUESTION:

71

\\

The range of values around the setpoint of a measured variable where NO ACTION occurs in an automatic flow controller is called:

A.

deviation.

l B.

crror.

l C.

deadband.

D.

bias.

l 1

l I

QUESTION:

72 L

The governor of an emergency diesel generator (D/0) DIRECTLY senses D/G and adjusts D/G flow to maintain a relatively constant D/G frequency.

A.

load, air i.

B.

speed, fuel C.

load, fuel D.

speed, air BWR FORM B 27

[.

=?

p.

r BWR FORM B

-QUESTION:

73 The output pressure of a pneumatic controller is typically insufficient to

{

l drive a valve. actuator accurately. To overcome this problem, a control loop would NORMALLY employ a:

A.

valve actuating lead / lag unit.

B.

pressure regulator, i

C.

valve positioner.

D.

filter drive unit.

QUESTION:

74 Which of the following changes in pump operating parameters will DIRECTLY lead to pump cavitation in a centrifugal pump that is operating in a closed loop system?

A.

Steadily increasing pump inlet temperature.

B.

Steadily decreasing pump flow rate (by reducing pump speed).

C.

Steadily increasing pump suction pressure, t

.D.

Steadily increasing pump discharge pressure,

. QUESTION:

75 Cas binding in a centrifugal pump can be prevented by prior.to pump start.

l A..

venting the pump B.

lowering suction pressure C.

throttling the discharge valve D.

shutting the discharge valve BWR FORM B 28 l-

t BWR FORM B QUESTION:

76, i

The correct way to start most LARCER motor driven' centrifugal pumps is with the pump discharge valve.

A.

in any position.

B.

throttled to midposition.

C.

fully open, f

D.-

fully closed.

l QUESTION:

77 i

A multispeed centrifugal pump is operating at 1800 rpm, providing a flow of 400 gpm at 20 psig.

If the pump speed is increased to 3600 rpm, the new pump discharge pressure will be:

A.

20 psig

-B.

40 psig i

C, 80 psig.

D.

160 psig QUESTION:

78 Which one of the following conditions will result in a DECREASE in the available recirculating pump net' positive suction head (NPSH)?

A.

Carry under decreases.

B.

Recirculation flow rate increases.

C.

Toedwater inlet subcooling increases.

D.

Feedwater flow rate increases.

SWR FORM B 29

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BWR FORM B QUESTION:

79 A constant speed centrifugal pump motor draws the LE&kI current when the pump

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is:

A.

at runout conditions.

B.

at operating conditions.

C.

accelerating to normal speed during start.

D.

at shutoff head.

I-QUESTION:

80 Failure to provide adequate minimum flow for a centrifugal pump can DIRECTLY result in:

A.

discharge piping overpressurization, b.

suction piping overpressurization.

C.

excessive pump leakoff.

D.

pump overheating.

l

' QUESTION:

81 s

A centrifugal pump is operating at rated conditions in a closed system with all' valves fully open.

If the pump suction valve is THROTTLED to 50 percent, pump discharge pressure will and flow will A.

increase; decrease B.

decrease; increase C.

increase; increase D.

decrease; decrease 1.

l BWR FORM B 30

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BWR FORM B QUESTION:

82 The main generator is connected to the grid. Which of the following characteristics will an UNDEPJ.KCITED generator exhibit?

A.

Negative megavars (vars in) and a leading power factor B.

Positive megavars (vars out) and a leading power factor C.

Positive negavars (vars out) and a lagging power factor D..

Negative negavars (vars in) and a lagging power factor s

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i BWR FORM B 31

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e BWR F03Gi 3 QUESTION:

83 A centrifugal pump has a flow rate of 3,000 gpm and a current requirement of 200 amps.

If the speed is reduced such that the flow rate is 2,000 gpm, what is the final CL'RRENT requirement 'at the new lower speed? (Assume a constant motor voltage.)

[

A.

59 amps B.

89 amps C.

133 amps D.

150 amps I

. QUESTION:

84 k'hich of the following is the reason for LIMITING the number of motor starts in a given time period?

'A.

Minimizes pitting of starter contacts B.

Prevents excessive torsional stresses on actor shaft C.

Prevents overheating of motor windings D.

Minimizes axial stresses on motor _ bearings

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l QUESTION:

85 If a locked rotor occurs on an operating motor driven pump, actor amps will:

A.

increase due to the decreased pump flow.

B.

increase due to the increased mechanical load, C.

decrease due to the decreased pump flow.

D.

decrease due to the' increased mechanical-load.

i BWR FORM B 32 r

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BWR FORM B QUESTION:

86 When placing a heat exchanger in service, care must be taken to introduce both

[

fluids gradually and simultaneously to:

A.

prevent excessive thermal stresses in the heat exchanger.

B.

maximize heat exchanger efficiency.

O.

minimize fouling of the heat exchanger tubes, j

D.

provide maximum control of cooling water outlet temperature.

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9 BWR FORM B 33

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BWR FORM B

. QUESTION: T87 Refer to the figure below for the following question. All valves are

-identival and are initially 50 percent open.

' To LO'a'ER the temperature at point l 7, the operator should adjust valve in the OflE direction.

.A.

A si B.

B

' C.'

C D.-

D

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O 3

[ C

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BWR FORM B 34

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BWR FORM B QUESTION:

88

- The Hal2E-thermodynamic concern resulting from RAPIDLY cooling a pressure J

vessel is:

A.

loss of subcooling margin.

B.-

the rmal ' shock.

i C.'

loss of shutdown margin.

D..

condensation.

QUESTION:

89,

- During normal reactor operation, a main condenser develops an air leak which decreases vacuum at'a-rate of 1 in. Hg/ min. Which of the following plant-parameters would be the EIEEI to show an INCREASE because of this condition?

_ A.

Extraction steam flow I

' b.

Generator megawatt output C.

-Circulating water outlet temperature D.

. Condensate temperature L

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BWR FORM B 35 a

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' QUESTION:

90.

' Refer-to the~ figure below for.the' following question, f

k'hich of the following effects would occur as a resu'lt of-a tube FAILUM in P

the heat exchanger?-

-A, High pressure fluid inventory increases.

{

1

- S.

Flow:in the low pressure system reverses.

CI.'

Temperature in the low pressure system increases.

.it D..

Level in the-tank increases.

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s BWR FOIUi B QUESTION 94 The temperature of the water passing through a demineralizer must be controlled because EXCESSIVELY HOT water:

A.

retains impurities, thereby reducing ion exchange.

'L.

is less dense, allowing less water to flow through the resin bea.

C.

' will result in demineralizer retention element thermal expansion, thereby releasing resin.

D.

will result in demineralizer resin decomposition, thereby reducing resin effectiveness.

QUESTION:

95 A result of proper demineralizer operation on water with impurities is that the exiting water will ALWAYS have:

A.

lower conductivity.

B.,

higher conductivity.

C.

lower pH.

'D.

higher pH.

-QUESTION:

96 During maintenance activities, breakers in the open position are TAGGED and RACKED OUT to:

A.

deenergizo components and associated control and indication circuits.

B.

provide administrative control where safety is not of prime importance.

C.

maintain remote indication of breaker position (where available) to ensure personnel-safety.

I D.

permit immediate availability of the breaker if required for emergency use.

BWR FORM B 38

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4 BWR F05G( B QUESTION:

91:

Proper venting of a shell-and tube heat exchanger is important because an air bubble':

-A.

redur,es the heat transfer ability of the heat exchanger.

B.

causes pressure. transients within the tubes as heat load changes.

C.

causes thermal shock es it moves through the heat exchanger.

D.

causes flow restriction within the heat exchanger.

QUESTION:

92 Channeling in a demineralizer is undesirable because:

A.

resin beads will' slump to the bottom of the domineralizer causing a flow blockage.

B.

portions of the resin will be completely bypassed causing outlet conductivity to increase.

l l

C.

the resulting high velocity fluid flow causes erosion of the resin beads

. and the release of ions.

D.

the resulting high velocity fluid flow can cause mechanical damage to system piping and components.

1 i

QUESTION:

93 The buildup of scale on heat-transfer surfaces in the reactor vessel:

A.

Lresults in lower fuel temperature, which decreases the nuclear fuel cycle efficiency.

L B.

is controlled by complying with core thermal limits and adhering to fuel preconditioning requirements.

C.

is controlled by using reactor water cleanup unit (RWCU) system and condensate system demineralizers.

D.

results in higher coolant temperature, which increases overall plant efficiency.

1 BWR FORM B 37 m

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BWR F050( B

-QUESTION:

97' Which-of the following local breaker indications would provide the HQ11 ACCURATE information for determining the position of a 4160 volt feeder breaker 7 i

A.

Overcurrent trip flags and load side voltage B.

OPEN/ CLOSED mechanical flag indication and load side voltage C.

OPEN/ CLOSED indicating lights and load side current D.

'Overcurrent trip flags and load ride current QUESTION:

98

.The function of high voltage electrical disconnects is to:

A.

isolate equipment electrically during no load conditions.

B.

isolate equipment electrically during overload conditions.

C.

protect circuits during overcurrent conditions.

D.

protect circuits during undervoltage conditions.

i QUESTION:

99-Which of the-following generator conditionn is MOST LIKELY__to cause generator damage because of high current?

A.

Tripping the output breaker under full-load conditions B.

Tripping the generator prime mover under full-load conditions-C.

Closing the output breaker on a bus that has an open-circuit fault D.

Closing the output breaker on a bus that has a short-circuit fault BWR FORM B 39 4

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BWR FORM B

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- QUESTION:

100-

. If a breaker _is racked in/out to the " test" position, the:

A.

normal breaker opening and closing operations cannot be tested because the test position is for overload testing only.

B.

-- breaker ean only be operated manually at the switchgear.

C.

remote position indication for the breaker is still operational.

D.

electrical jumpers must be connected to the operating coils to operate the breaker.

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BWR FORM B 40 1

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