Text

Forwards Oct 1997 Generic Fundamentals Exam & Answer Key to Be Placed in PDR
	ML20199B481
Person / Time
Issue date:	11/13/1997
From:	Sandra Figueroa; NRC (Affiliation Not Assigned)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9711190004
	Download: ML20199B481 (143)
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UNITED $TATES p+

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NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. Me6Mm01

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November 13, 1997 NOTE T0:

Documert Control Desk fijlIehafi[IbEf7b' Assistant fROM:

Sa Division of Reactor Controls and Human factors Operating Licensing Branch

SUBJECT:

OCTOBER 1997 GENERIC TVNDAMENTALS EXAMINATION (GfE)

Enclosed please find the October, 1997 GFE examination and answer key to be placed in the PDR.

If you have any questions I can be contacted at 415-1065.

Enclosure:

As stated

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UNITED STATES NUCLEAR REGULATORY COtetISSION PRESSURIEED NATER REACTOR GENERIC FUNDAMENTALS EY uINATION OCTOSER 1997 - FORM A l

September 12, 1997 Please Print Name Facility:

Docket No.:

Start Time Stop Times INSTRUCTIONS TO APPLICANT Answer all the test items using the answer sheet provided.

Each item has equal point value.

A score of at least 80% is required to pass this portion of the written licensing examination.

All e

examination papers will be collected 3.0 hours0 days 0 hours 0 weeks 0 months after the examination starts.

This Examination applies to a

typical pressurized water reactor (PWR) power plant.

1 SECTION QUESTIONS

% OF TOTAL SCORE COMPONENTS 1 - 44 REACTOR THEORY 45 - 72 THERMODYNAMICS 73 - 100 TOTALS 100 All work done on this examination is my own.

I have neither given nor received aid.

Applicant's Signature

i RULES AND GUIDELINES FOR THE l

GENERIC FUNDAMENTALS EXANINATION t

During the administration of this examination tha following rules apply:

\\

NOTE:

The generic term

control rod" refers to the length of i

neutron absorber material that can be positioned by the

-operator to change core reactivity.

~

1.

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

l 2.

Fill in the name of your facility.

3.

Fill in your individual docket number.

4.

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

5.

Two aids are provided for your use during the examinations (1)

An equations and conversions sheet contained within the examination-copy, and (2)

Steam tables provided by your proctor.

6.

Place your answers on the answer sheet provided.

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

Follow the instructions for filling out the answer cheet.

9

'/.

Scrap paper will be provided for calculations.

6.

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

Cheating could also result in severe penalties.

9.

Restroom trips are limited.

Only ONE examinee may leave the room at a time.

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

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

11. Turn in your examination materials, answer sheet on top, followed by the examination booklet, then examination. aids -

steam table booklets, handouts and scrap paper used during the examination.

12. After turning in your examination materials, leave the examination area, as defined by the proctor.

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

i GENERIC FUNDhMENTALS EXABRIIthTION e

500ATIONS Aun coer/ERSIoses MANDOtFP SERET EQUATIOeBS O = rhe,AT P = P 10smo O = thah P = P e "

o Q = UAaT A = A,e-^t Q4 CReft, = S/ (1 - Kerr)

CR (1 - K rra) = CR (1 - Kerra) e N"

are 1/M = CR /CRx K.tr = 1/(1 - p) 1RW= $b,/ $,,,

2

.p=

(K.tr - 1) /K.tr SUR = 26.06/t rh = pAV

_0P T*

W%= rhAPU A

p E = IR P " t' p

+

g4 A Eff. = Net Work Out/ Energy In 9

8 ~ * *

~

l' = 1 x 10** seconds 2g, g,

A.r g = 0.1 seconds **

32.2 lbm-ft/lbf-sec' ge u CONVERSIONS 1 MW 3.41 x 10' Btu /hr 1 Curie

=

3.7 x 1088 dps

=

1 hp 2.54 x 108 Btu /hr 1 kg

=

2.21 lbm

=

1 Dtu =

778 ft-lbf 1 gal..t.,

~

8.35 lbm

=

'C (5/9) (*F - 32) 1 f t*,,t.,

=

7.48 gal

=-

F (9 / S ) ( *C) + 32

=

3-L l

~

'i e

USMRC GENERIC FUNDhimbrFAT,8 EIANIIIATION OCTOBER 1997 PWR - FORM A e

QUESTION:

1 TOPIC:

191001 KNOWLEDGE:

Kl.02 QID:

P1504 1

Which one of the following is a difference between a typical relief valve and a typical safety valve?

A.

The actuator closing spring on a relief valve is in a compressed state whereas the actuator closing spring on a safety valve acts in tension.

B.

A relief valve gradually opens as pressure increases above the setpoint pressure whereas a safety valve fully opens at the setpoint pressure.

C.

Relief valves are capable of being gagged whereas safety

[

-valves are not.

D.

The blowdown of a relief valve is greater than the blowdown of a safety valve.

ANSWER:

B.

QUESTION:

2 TOPIC:

191001 KNOWLEDGE:

Kl.07 OID:

P503 (rev)

Which one of the following valves is used to control the direction of fluid flow and prevent backflow in a system?

A.

Gate valve B.

Relief valve-C.

Globe valve D.

Check valve ANSWER:

D..

~

USNRC GENERIC FUNDAMENTALS EXAMINATION OCTosER 1997 PNR - FORN A QUESTION:

3 TOPIC:

191001 KNOWLEDGE:

K*. 08 QID:

P1405-1 Refer to the cutaway-view drawing of a valve (see figure below).

Which one of the following describes the type of valve shown?

A '.

Rising-stem gate valve B.

Nonrising-stem gate valve C.

Rising-stem globe valve D.

Nonrising-stem globe valve ANSWER:

B.

w-x

/

JN

(

e

$y C

h 9

VD W

% ((b

'W I

(

A

\\

VALVE CUTAWAY VIEW

_g.

-... - ~..

. - = - -..

1 USMRC GEMkRIC FUNDhMENTALS REMtIMATI0tt-l OCTOBER 1997 PWR - FORM A l

i QUESTION:

4

' TOPIC:

191001 KNOWLEDGE:

Kl.09-

[

QID:

P1104 (Rev)

Gate-valves generally are not used to throttle fluid flow I

because l

A.

rapid changes in fluid direction through the valve cause a large unrecoverable system head loss.

B.

gate valves experience stem leakage when partially open.

(

C.

the turbulent flow created by a partially opened gate valve causes excessive oeat and disk wear.

D.

the large size of the valve disk requires an oversized i

actuator to position the valve accurately.

ANSWER:

C.

I QUESTION:

5 TOPIC:

191002 KNOWLEDGE:

Kl.02 QID:

P705 A steam flow measuring instrument uses density compensation and square root extraction to convert the differential pressure 1

across the flow element to lbm/hr.

The purpose of square root extraction in this flow measuring instrument is to convert to A.

Volumetric flow rate; mass flow rate f

B.-

volumetric flow rate; differential pressure

-C.

differential pressure; mass flow rate D.

differential pressure; volumetric flow rate ANSWER.

D.-

T 6

M M

?

r L

.,--..e._.

.,,,r R.,.

.m

. a..

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

.4 4

i l

USNRC GitalERIC FUNDAMENTALS EXAMINATION Oc1OBER 1997 PWR - FORM A QUESTION:

6 I

TOPICS 191002 i

KNOWLEDGE:

r,1.04 OID:

P1608 Refer to the drawing of a horizontal pipe elbow (top view) in an operating water system (see figure below).

Three separate-bellows differential pressure flow detectors are connected to taps A,- B, C, and D as follows:

DETECTOR TAPS

~

AD A and D BD B and D CD C and D Assuming zero head loss in this section of pipe, how will the detectors be affected if tap D ruptures?

A.

All detectora wi11 fail low.

B.

All detectors will fail high.-

C.

Two detectors will fail low and one will fail high.

D.

Two detectors will fail high and one will fail low.

ANSWER:

A.

tti w

OA e

c

[

ll FLOW b --

o PIPE ELBOW. TOP VIEW i

+

7-

. _ -. =. -

i USNRC GENERIC FUtfDAMERITAL5 EXAMIIthTIOtt OCTOBER 1997 PWR - FORM A QUESTION:

7 TOPI(!:

191002 i

KNOWLEDGE:

K1.05 QID:

P908 i

Which one of the following flow measuring devices produces the largest unrecoverable head loss when used in an operating fluid system?

A.

Orifice.

l B.

Venturi r

C.

Pipe elbow I

t D.

Flow nozzle ANSWER: A.

QUESTION:

8 TOPIC:

191002

+

KNOWLEDGE:

K1.17 QID:

P1612 A reactor is shut down at 100 cps in the source /startup range when a loss of coolant accident occurs.

Which one of the following describes excore source /startup range neutron level indication as homogeneous core voiding increases from 20% to 40%?

l i

A.

Increases because more neutron leakage is occurring l

B.

Decreases because less neutron leakage is occurring C.

Increases because Kerr is increasing D.

Decreases because K rr is decreasing e

ANSWER:

A.

l 8-

L USafRC OENERIC FUNDAMENTAL 5 EXAMINATION OCTOBER 1997 FNR - FORM A QUESTION:

9 TOPIC:

191002 KNOWLEDGE:

K1.06 QID:

P608 (Rev)-

Refer to the drawing of two tank differential pressure (D/P) level indicators (see figure below).

Twc, D/P level indicators are installed on a large water storage tank.

Indicator 1 was calibrated at 100'F water temperature and indicator 2 was calibrated at 200'F water temperature.

Assuming both are on scale, which indicator will' indicate the higher level?

A.

Indicator 1 at all water temperatures B.

Indicator 2 at all water temperatures C.

Indicator i below 150*F, indicator 2 abov9 150*F D.

Indicator 2 below 150*F, indicator 1 above l'.,*F ANSWER:

B.

toANd!ne WATER

/

Os

/

ee.

T ANK DIFFERENTIAL PRESSURE LEVEL INDICATORS h

em i

.-. _ - =. _.. _.

l USNRC QENERIC FUNDAMENTALS RIANIMATION l

OCTOBER 1997 PNR - FORN A l

QUESTION:

10 TOPIC:

191002 v

KNOWLEDGEs. Kl.08 QID:

NEW Refer to the drawing of a tank with a differential pressure level detector (See figure below.).

The level detector was calibrated with reference leg and tank contents temperature at 70'F.

An increase in ambient temperature causes the temperature of the reference leg and tank contents to increase to 110*F.

+

With the temperature of the reference leg and tank contents otable at 110*F, current level indication will be A.

higher than initial due to reference leg spill over.

B.

higher than initial due to expansion of tank contents.

C.

the came as initial due to offsetting density changes in the reference leg and tank contents.

D.

the same as initial due to the reference leg being connected to the upper portion of the tank.

ANSWER:

A.

REFERENCE LdG FILL CONNECTION j

GAS OR VAPOR PRESSURE 5

^

EQUAllZlNG h

VALVE s

n

/

0 DETECTOR TANK DIFFERENTIAL PRESSURE LEVEL DETECTOR '

USNRC GENERIC FUPDAMENT.%8 EXAMINATION OCTOBER 1997 FNR - FORM A i

QUESTION:

11 TOPIC:

193002 KNOWLEDGE:

K1.12 i

QID:

P510 (Rev)

Refer to the drawing of a bellows-type pressure detector (see figure below).

f A bellows-type pressure detector with its low-pressure side vented to containment at'nosphere is being used to measure pressurizer pressure.

A decrease in the associated pressure indication will be caused by either a containment pressure or a i

A.

increase; ruptured bellows i

B.

increase; broken spring C.

decrease; ruptured bellows D.

docrease; broken spring ANSWER:

A.

/ MOVEABLE WALL i

SEAthG

[

)

MLM L

/

LOW PRtstuRE -

/j CONNECil0N L

.at0We L'"."*

uews. m..= mma

.I.

i CSNRC GENERIC FUNDMtENTALS EXAMINATION l

OCTosta 1997 Fwn - yonN A QUESTION:

12 TOPIC:

151002 KNOWLEDGE:

K1.13 OID:

P1412 (Rev) i Refer to the draMing of a simple thermocouple circuit (see figure below)

Circuit temperature indicat3 n is currently 350*F.

If an ambient temperature decrease lowers reference (cold) junction temperature by 10*F, the new temperature indication will ber (Asstune measuring junction temperature remains constant.)

A.

340'F.

D.

350*F.

C.

360*F.

D.

370*F.

ANSWER:

C.

3 VOLTAGE JUWTION O

REFERENCE (COLC)

TSWNM JUNCTION (TEMPEMATURE INDICAflON)

SIMPLE THERMOCOUPLE CIRCulT PROOF:

T na = Tu - Te i

If Te decreases by 10*F, then T a increasec by 10'F.

in 350*F + 10*F = 360*F c _ --

USNF.C GENERIC FUNDhB8 ENTAL 5 EXANINATION OCTOBER 1997 FWR - FORN A I

QUESTION:

13 TOPIC -

191002 KNOWLEDGE:

K1.20 OID:

P1114 Which'one of the following describes the' source of ions collected in a proportional counter (BF detector)?

3

~

i A.

A' fraction of tha ions created by primary lonizations are l

collected.

No secondary lonizations take place.

B.

Virtually all o'-the ions created by primary lonizations are

[

collected.

No secondary lonizations take place.

C.

Virtually all of the ions created by primary lonizations along with a fraction of the ions created by secondary ionizations are collected.

j i

-D.

Virtually all of the ions created by primary and secondary lonizations are collected.

ANSWER:

D.

QUESTION:

14 TOPIC:

191002 KNOWLEDGE:

X1.19 QID:

NEW An initial radiation survey is about to be perfortaed in an area of unknown radiation field intensity.

Which one of the following types of radiation monitoring instruments and settings should be used?

A.

A Geiger Mueller survey meter selected to the low range B.

A Geiger Mueller survey meter selected to the high range i

C.

An ion chamber survey meter selected to the low range D.

An'lon chamber survey meter selected to the high range ANSWER -D.

K y a>

USNRC raiennemIC FUNDhttENTALS EXAMINAT100f OCTOBER 1997 PWR - FORM A QUESTION:

15 TOPIC:

191003 KNOWLEDGE:

Kl.02 QID:

P218 An emergency diesel generator (D/G) is operating as the only I

power source connected to an emergency bus.

The governor of the i

D/G directly sensos D/G and directly adjusts D/G flow to maintain a relatively constant D/G frequency.

A.

speed; fuel D.

speed; cir C.

load; fuel

,D.

load; air ANSWER:

A.

QUESTION:

16 TOPIC:

191003 KNOWLEDGE:

Kl.05 QID:

P1618 (Rev)

An sir-opereted isolation valve requires 2,800 pounds-force (lbf) from its diaphragm actuator and 4 inches of stem travel for proper operation.

The valve positioner can supply a nominal 117 psig of air pro.t t,1*.re to the actuator, i

What is the minimum surface a ea of the actuator diaphragm required for proper valve operation?

A.

24 square inchus D.

48 souara inches C.

94 squa.re inches D.

138_squarn inches

~

ANSWER:

A.

' PROOF:

F = PA A=E=

2800 #

= 24 i n 2 P

117 #/ i n 8

USNRC GENERIC FUNDAMEFFALS EXAMINATION OCTOBER 1997 PNR - FORN A QUESTION:

17 7

TOPIC:

191003 KNOWLEDGE:

Kl.06 QID:

P2018 i

A diesel generator is supplying a bus with the governor operating in the isochronous mode.

If a larga electrical load on the bus trips, generator frequency will 1

A.

initially increase, and then decrease and stabilize below the i

initial value.

i B.

Initially increase, and then decrease and stabilize at the initial value.

C.

initially increase, and then decrease and stabilize above the initial value.

D.

remain constant during and after load change.

t ANSWER:

-B.

QUESTION -

18 TOPIC:

191003 KNOWLEDGE:

Kl.08 QID:

P917 Which one of the following describes the response of a direct-acting derivative controller, operating in automatic, to an increase in the controlled parameter above the controller set point?

A.

The controller will develop an output signal that continues to increase until the controlled parameter equals the controller set point, at which time the output signal becomes constant.

i B.

The controller will develop an output signal that will remain directly proportional to the difference between the controlled parameter and the controller set point.

C.

The controller will develop an output signal that continues to increase until the controlled parameter equals the controller _aet point, at which time the output signal becomes zero.-

D..The controller will develop an output signal that will remain directly proportional to the rate of change of the controlled parameter.

ANSWER:

D.

_ _. _ _.__ _...._-~_-. _.._

USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PNR - PORN A

[

QUESTION:

19 TOPIC:

191003 KNOWLEDGE:

Kl.ll QID:

P19

{

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

)

I A.

'Hanual valve controller operation can result in excessive valve cycling.

B.

Valve position will no longer automatically change in response to changes in system parameters.

C.

System parameters will no longer automatically change in response to changes in. valve position.

D.

The valve can only be operated locally during manual controller operation.

l ANSWER

.B.

QUESTION:

20 TOPIC:

191004 KNOWLEDGE:

Kl.07 QID:

P24 Shutting the discharge valve on an operating centrifugal pump will cause the motor amps to and the pump discharge pressure to A.

increase, increase-

. B.

decrease, increase C.

increase, decrease D.

decrease, decrease

- ANSWER:

B.

i.

.. - =

i USMRC OEMERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 FNR - FORN A j

QUESTION:

21 TOPIC:

191004 KNOWLEDGE:

K1.04 OIDs.

P1320-(Rev) r Refer to the drawing of a pump with a recirculation line (see figure below).

Valve "A" will open when pump:

A.

discharge pressure reaches a high set point.

B.

discharge pressure reaches a low set point.

C.

Clow rate reaches a high set point.

D.

flow rate reaches a low set point.

ANSWER:

D.

A g.; -- ----..

A've

_1,

,,c, l

t 9

e.

r

, ase noe SUCTION PUMP PUMP WITH RECIRCULATION LINE i

-~17 -

- -. =

t I

C5MRC QENER%C FUNDhMENTALS EXJW1MATION OCTOBER 1997 PWR - FORM A j

QUESTION:

22 TOPIC:

-91004 KNOWLEDGE:

K1.06 QID:

P1221 (Rev)'

Refer to the drawing of a cooling water system (see figure below).

The available net positive auction head for the centrifugal pump will be decreased by:

A.

increasing surge tank level by 5 percent.

B.

throttling heat exchanger cooling water valve "B" more open.

C.

throttling punop discharge valve "C" more closed.

D.

increasing the heat loads on the coo 31ng water system.

ANSWER: D.

6 A

c p

~

TANK

.ra=<

.u e

WATER MAREUPI 74

)'

go 5 =.

CE o

PUMP COOLING WATER SYSTEM 4

18 -

USMRC OEMEIGC FUNDhMENTALS EXAltIMATIOtt

{

OCTOBER 1917 FMR - FORM A

-QUESTION:

23 TOPIC:

191004 KNOWLEDGE:

Kl.03 QID:

NEW f

-.A contrifugal pump is operating-in parallel with a positive displacement pump in an oper4 system.

Each pump has the fame design pressure.

7 i

If pump discharge pressure increases to the maximum design pressure of each pump, the centrifugal pump will be operating at flow and the positive displacement pump will be operating at flow.-

A.

minimum; minimum-B.

minimums rated C.

rated; minimum I

D.-

rated; rated ANSWER:

B.

QUESTION:

24 TOPIC:

191004 KNOWLEDGE:

K1.35 QID:

P1421 (Rev)

A motor-driven centrifugal pump is cperating in an open system with its discharge valve throttled to 50%.

How will the pu np be affected if the discharge. valve is fully opened?

.A.

Motor current decreases and total developed head decreases.

B.

Available net positive suction head (NFSH) decreases, and P

pump differential pressure decreases.

C.

Total developed head increases and available NPSH decreases.

D.

The potentiel for pump cavitation decreaseb, and pump differential pressure decreases.

ANSWER:

B.-.

a._ ; -

z..

. ~. -.

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

USNRC GENERIC FUNDMGNTALS EXANINATION OCTosER 1997 PNR - FoRN A I

i QUESTION:

25 TOPIC:

191004 KNOWLEDGE:

Kl.12 QID:

P1721

-Rofer to the drawing of a centrifugal pump operating curve (see figure below).

Which point represents pump operation at runout conditions?

l A.

Point A B.

Point B

.C.

Point C D.

Point D ANSWER:

C.

POINT A

/

1 PUMP POINT B HEAD POINT D POINT C

/_

/

FLOW d

CENTRIFUGAL PUMP OPERATING CURVE,

. - - _ _ =, -

~- - -. _-_

... =. - -.

USNRC GENERIC FtBEDAMENTALS REANIMATION OCTOBER 1997 PWR - FORN A QU0STION:

26 TOPIC:

191004 KNOWLEDGE:

K1.21 QID:

P1425 l

Which one of.the following describes the proper location for a I

relier valve that will be used to prevent exceeding the design pressure of a positive displacement pump and associated piping?

On' the pump suction piping upstream of '

.3 suction isolation i

r.

valve B.

On the pump suction piping downstream of the suction l' solation valve C.

On the pump discharge piping downstream of the discharge isolation valve D..

On the pump discharge piping upstream of the discharge, isolation valve ANSWER:

D.

QUESTION:

27 TOPIC' 191005 KNOWLEDGE:

K1.02 QID:

PS28 Which one of the following will provide motor protection against electrical damage caused by gradual bearing degradation?

A.

Thermal overload device B.

Overcurrent trip relay f

C.

Underfrequency relay D.

Undervoltage device ANSWER:

A.

t '

2

s U53tRC GENERIC FUNDAMENTALS EXAMINATIOtt OCTOBER 1997 PWR - FORM A

~

QUESTION:

28 TOPIC:

191005 KNOWLEDGE:

Kl.03 QID:

P1529 (Rev) 1A diesel-generator 1(D/G) is supplying an electrical bus in parallel with the grid.

Assuming'D/G terminal voltage and bus frequency do not change, if the D/G governor set point is increased-from 60.0 Hz to 60.1 Hz, then D/G kVAR will and D/G: amps will A.

remainfthe same; increase i

B.

remain the same; remain the same L.

increase; increase D.-

increase; remain the same F

ANSWER:

A.

QUESTION:

29 TOPIC:

191005 KNOWLEDGE:

Kl.04 QID:

P630 (Rev)

Which one of the following describes the motor current indications that would be observed during the start of a large ac motor-driven centrifugal pump with a closed discharge valve?

-A.

Current immediatel; increases to the full-load value and then decreases to the no-load value over several seconds.

B.

Current immediately increases to the no-load value and then stabilizes.

C.

Current immediacely increases to gteater than the full-load value and then decreases to the no-load value after several seconds.

D.

Current immediately increases to greater than the full-load l.

value and then decreases to the no-load value after several minutes.

ANSWER:

-C. - -

USMRC GENERIC FUNDAbMNTALC EXAMINATt,0N OCTOBER _1997 PWR FORM A QUESTION:

30 TOPIC:

191005 KNOWLEDGE:

K1.05 QID:

NEW Two identical 4160 Vac induction motors are connected to

-identical centrifugal pumps being used to provide. cooling water-flow-in separate-systems in a power plant.

F ica. motor isfrated at 1000 hp.

The discharge valve for pump A.ts fu,1y open_and the discharge valve--for pump B is fully shut.

If each. motor is then started, the longest time period required-to stabilize motor current will be experienced by motor and the higher stable motor current will be experienced by' motor A.

A; A B.

A; B C.

B; A D.-

B; B ANSWER:

QUESTION:

31 TOPIC:

191005 KNOWLEDGE:

K1.06 QID:

P1031 The number of starts for'an electric motor in a given period of ttes should be limited because overheating of the c... t accur due to the counter electromotive force prc4uced at low rotor speeds.

A.

windings; low B.-

windings; high C.

-commutator and/or_ slip rings; low D.

commutator and/or slip rings; high' ANSWER:

A, i

I l :-

l

USNRC GENERIC FUNDANENTALS EXAM 7, NATION OCTOBER-1997 PWR - FORM A QUESTION:

32.

TOPIC:

191006.

KNOWLEDGE:

K1.07 QID:

P1634 (Rev)

Refer to the drawing of a lube oil heat exchanger (see figure below).

Given the following existing conditions:

dgti

1. 8 x 10' lbm/hr

=

ri

.t.,

= 3.3 x 105 lbm/hr t

C.oit

= 1.1 Btu /lbm 'F p

C.,.tu = 1.0 Btu /lbm "F p

A.i.

= 90'F T. ot

= 120*F o

T

= 190*F oit.g.

T 7

oit-out Which one of the following is the temperature of the oil exiting the heat exchanger (Toti.out) ?

A.-

110*F B.

120*F C.

130*F D.

140*F ANSWER:

D.

LUBEOtlHEATEXQtANMR..

USNRC GENERIC FTIKDfJMNTALS EXAMINATION OCTOBr.k 1997 PWR - FORM A PROOF:

mcAT

= mc6T AT.33 mcoT/mc

=

T gg.ous

= T g3 1, -(meat /me) o o

T

= 190 - (3. 3 ) (1. 0) (3 0) oi3.,

(1. 8 ) (1.1)

= 140*F QUESTION:

33 TOPIC:

191006 KNOWLEDGE:

K1.12 QID:

P32 (Rev)

Refer to the drawing of a lube oil heat exchanger (see figure below).

If deposits accumulate on tne outside of the cooling water tubes, cooling water outlet temperature will and oil outlet temperature will (Assume oil and cooling water flow rates remain the same.)

A.

increase; decrease B.

increase; increase C.

decrease; decrease D.

decrease; increase ANSWER:

D.

LUBE 0tL HEAT EXCHAMEll 25 -

~..

USNRC GENERIC FUNDAME3fTALS EXAMINATION OCTOBER 1997'PWR FORM A:

QUESTION:

34 TOPIC:

191006

~ KNOWLEDGE:

K1.08 QID:

-P1732 Which one of the following will reduce the rate of heat transfer between two liquids in a heat exchanger? (Assume single-phase conditions and a constant specific heat for both liquids.)

.A..The' inlet temperctures of both liquids are decreased by 20'F.

~

B.

The inlet temperatures of both liquids are increased-by-20'F.

C.

The inlet temperature of the hotter liquid is increased by 20*F.

D.

The inlet temperature of the colder liquid is increased by 20*F.

ANSWER:

D.

-.A

.-h,i 4

s J

h M

~, - ', -

-USNRC GENERIC-FUNDAMENTALS EXAMINATION ^

OCTOBER 1997 PNR - FORN A QUESTION:

35 TOPIC:

191007 KNOWLEDGE K1',01 ~

_QID:

P1736~(Rev)-

A condensate.demineralizer-differentiai-pressure (D/P)= gauge-indicates 4 paid'at-50%' flow rate.

Which one of the following combinations-of condensate-flow and demineralizer D/P observed at various' power levels indicates an increase in the accumulation of

-insoluble corrosion products in the demineralizer?-

CONDENSATE DEMINERALIZER FLOW D/P (PSID)

'A.

25%

1.0 B.

60% -

6.0 1

C.

75%

9.0 D.

100%

15.0 ANSWER:

B.

PROOF:

F = N; H = Na i

(F /F )'

H /H =

3 2

Ha = H (F /F )2 3

3 025% flow, D/P should be 1.0 psid 060% flow, D/P should be 5.76 psid 975%' flow,- D/P should be 9.0 psid 0100%. flow, D/P should be 16.0 psid Only choice.B exceeds the expected D/P.

USNRC GENERIC FUNDAMENTALS EXAMINATION OCTO ER 1997 PNR - FORM A QUESTION:

36

-TOPIC:

191007 KNOWLEDGE = Kl.03 QID-P936 (Rev)

ToLdetermine the-demineralization factor for a demineralizer, the parameters that must be monitored are inlet and outlet A.

pH B.'

conductivity C.

suspended solids D.

pressure ANSWER:

B.

4 QUESTION:

37 TOPIC:

191007 KNOWLEDGE:

Kl.14 QID:

P1335 The plant is operating at 70% stable power level when the temperature of reactor coolant letdown passing through a boron-saturated mixed bed ion exchanger is increased by 20*F.

As a result, the boron concentration in the effluent of the ion exchanger will because the affinity of the ion exchanger for boron atoms has A.

decrease; decreased B.

decrease; increased C.

' increase; decreased D.

increase; increased ANSWER:

C. _

4 USNRC-GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PNR - FORM A QUESTION:'

38

. TOPIC:

191008-

-KNOWLEDGE:

Kl.04 QID:

P2041 Two: identical-1000 Mw electrical generators are-operating in parallel supplying the same electrical _ bus.

The generator output breakers also provide identical protection for the generators.

Generator A and B output indications _are as follows:

Generator A

, Generator B 4160 Volts 4160 Volts

'0.2 Hertz 60.2 Hertz 6

50 Mw 100 Mw 25 MVAR (out) 50 MVAR (out)

A malfunction causes the voltage regulater setpoint for generator B to slowly increase continuously toward a maximum of 4400 voltc.

If no operator action is taken, which one of the following describes-the current indications for generator A?

A.-

Current _will decrease continuously until the output breaker for generator B trips on reverse power.

B.

Current will-decrease continuously until the output breaker for generator A trips on reverse power.

C.

Current will initially decrease, and then increase until the output breaker for generator B trips on overcurrent.

D.

Current will initially decrease, and then increase until the output breaker for generator A trips on overcurrent.

ANSWER: C.

l l.

.r4

. - =..

.x.-

.e

,- e USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOZER-1997 PWR - FORM A QUESTION:

39 TOPIC:

191008 KNOWLEDGE:

K1.06 QID:

P1739 (Rev)

Refer to the drawing of a valve motor control circuit (seeffigure below) for a valve that is currently fully open.

Which one of the following describes the valve response if the control switch is taken to the "Close" position for two seconds and then released?

A.

The valve will not move.

B.

The. valve will close fully.

C.

The valve will begin to close and then stop moving.

D.

The valve will begin to close and then open fully.

ANSWER:

C.

+125 VDC Neut:31 Neutral

% em-.3

% m.en.>

O O

O ".. 9........ 9...

0 K

(R)

(G)

Kl.2, Open Close Open Clase Alarm j T

/

_ lst

_ J32 w

_ l34 W

~~

~'

Opes When Open Wiwa Open Hben Open When Open When Valw Feay Open Valw Fou Ossed Yaho Feny Valu Fa#y Vain Foty r

O '"

O'**d O en P

P K21 Kl 1 A

1-

-A

-/-

El K2 fOrahy f0== hr VALVE MOTOR CONTROL CIRCUIT 30 -

c USNRC GENERIC FUNDAMENTALS-EXAMINATION OCTOBER 1997 PNR - FORN-A 1

QUESTION:

40 TOPIC:

191008-

-KNOWLEDGE: -Kl.08 QID-P1842-(Rev)

A-main generator is being prepared for paralleling with the grid.

Which one of:the following indicates that the main generator and grid voltages are in phase?

A.

The voltage of the generator is equal-to the voltage'of the

. grid.

B.

The frequency of the generator is equal to the-frequency of the grid.

C.

The synchroscope is turning slowly in the clockwise direction.

D.-

The aynchroscope is passing through the 12 o' clock position.

ANSWER:

D.

QUESTION:

41 TOPIC:

191008 KNOWLEDGE:

Kl.08 QID:

P2040 A main generator is being prepared for paralleling with the grid.

Which one of the following conditions will cause the main generator to immediately supply reactive power (MVAR) to the grid when the generator output breaker is closed?

A.

Generator voltage is 1% higher than grid voltage.

B.

Generator voltage is 1% lower than grid voltage.

C.

.The synchroscope is turning slowly in the clockwise direction.

D.

The synchroscope is turning slowly in the counterclockwise i

direction.

ANSWER:

A.

I,

1 l

~-

..[* e USNRC GENERIC FUNDAMENTALS EXANINATION

_ OCTOBER-1997 PNR - FORN A QUESTION:

~4 2

-TOPIC:

191008 KNOWLEDGE:- Kl.ll 1

?QID P1932 I

-While remotely investigating the condition of a normally-open motor' control center (MCC) feeder breaker, an. operator observes the following indications:

Green breaker position indicating _ light is out.

Red breaker position indicating light is lit.

MCC voltmeter indicates normal voltage.

MCC ammeter indicates zero amperes.

. Based on these indications, the operator should report that the circuit breaker is and racked A.

open;-in B.

closed; in C.

open; to the test position D.

closed; to the test position ANSWER:

B.

QUESTION:

43 TOPIC:

191008 KNOWLEDGE:

Kl.10 QID:

P943 What is an advantage of using high voltage electrical disconnects instead of circuit breakers to isolate main power transformers?

A.

Disconnects provide positive visual indication that the circuit is broken.

.B.

Disconnects can be operated either locally or remotely.

C.

Disconnects-are cheaper and provide the same protection as a breaker.

D.

Disconnects are capable of passing a higher current with less heating than a breaker.

ANSWER:

A. 1 a.

l,

USIOlC GENERIC FUNDMEENTALS EXANINATION -

OCTOBER.1997 PNR - FORN A.

QLSTION:

44-

= TOPIC:

191008.

KNOWLEDGE: . Kl'; O 8 QID:

P2 04 4 ' - (Rev) '

An isolated electrical bus is being supplied by generator A.

Generator B'is about to be connected to the same electrical bus..

Generators A and B are both rated at 1000 Mw.

Generator A and B

' output indications are as-follows:

Generator A Generator B 4140 Volts 4160 Volts 60.8 Hertz 60.2 Hertz 25Mw 0 Mw

'10'MVAR 0 MVAR When the output breaker for generator B is closed, which generator is more likely to trip on reverse power?

A.

Generator A due to the lower initial voltage B.

Generator A due to the higher initial frequency C.

Generator B due to the higher initial voltage D.

Generator B due to the lower initial frequency ANSW2R: D..

USNRC OENERIC FUNDAMENTALS EXAMINATION-OCTOBER-1997 PWR - FORM-A

-QUESTION:.

'45 TOPIC:

192001 KNOWLEDGE:

K1. 02.

QID' P1245 As compared-to a prompt neutron. a delayed neutron, born from the Same. fission. event, iS'more likely'to:

A.-

leak out of-the core.-

B.

be absorbed in the moderator.

C.

be captured by a U-238 nucleus.

D.

cause fission of a U-235' nucleus.

ANSWER:

D.

- 34.-

I

~

~.. -

USNRC GENERIC-FUNDAMENTALS EXANINATION OCTOBER'1997 PWR - FORM A-QUESTION:

46 TOPIC:

192002 YNOWLEDGE. K1.13 QID:

P1446 A reactor at the beginning of core life has been shut down from 100% power and cooled down to_340*F over three days.

During'the cooldown, boron concentration was increased by_200 ppm.

Given the following absolute values of reactivities added during the shutdown and cooldown,,' assign a (+) or (-) as appropriate and choose the current value of shutdown margin.

Xenon

= () 3.0% 6K/K..

Boron

= ( ) 3.5% AK/K Power defect = ( ) 4.0% AK/K Rods

( ) 7.0% AK/K-

=

Cooldown

=( ) 2.0% AK/K A.

-1.5% AK/K B..

-2.5% AK/K C.

-7.5% AK/K D.

-9.5%-AK/K ANSWER:

A.

PROOF:

s

. Xenon

(+) 3.0% ok/k

=

Boron

=-(-) 3.5% Ak/k Power D

=

(+) 4.0% ok/k Rods

(-) 7.0% ak/k

=

Cooldown = (+) 2.0% ok/k SDM

=

(-) 1.5% ak/k,

- _ -....- -~

.~

)

4 USNRC ramsERIC FUBmMEEbrtALS EXAMINATION OCTOBER 1997 PNR --FORM A

' QUESTION:~

-47 TOPICS.

192002 KNOWLEDGE:

K1.14-QID:

NEW P

A reactor is operating at 60%' power when the operator adds 10 gallons of boric acid to the reactor coolant system (ROS).

Over the next several' minutes, the operator-adjusts control rod

. position as necessary to maintain a constant reactor coolant average temperature.

When the plant stabilizes, shutdown margin will be

~

and axial power' distribution will have-shifted toward the of the core.

A.

the'same; top B.

the same;-bottom C.

larger; top D.

larger; bottom ANSWER: C.

a l <.

r~<

,.e e-a g

USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 FWR -' FORM A QUESTION:

48 TOPIC:

_192003 KNOWLEDGE: -K1.01 QIDt NEW Two reactors _ are currently: shut down with a reactor stactup in-progress. The two reactors are' identical except that reactor A has a source neutron strength of 100_ neutrons per second and reactor B' source neutron strength is 200 neutrons per second.-

Control rods are stationary and Keff is 0.98 in both reactors.

Core neutron level has reached. equilibrium in both reactors.

Which one of'the following lists the-core neutron level (neutrons per-second)- in reactors A and B?

Reactor A Reactor B A.

-5,000 10,000 B.

10,000 20,000 C.

10,000 40,000 D.-

20,000 40,000 ANSWER:

A.

PROOF:

CRsto S/(1-K)

Reactor A CRa,o = 100/.02

= 5,000 Reactor B CR,o = 200/,02-

= 10,000

. V

i,

-e USMRC QENERIC FUNDAMENTALS EXAMINATION

_ OCTOBER 1997 PWR - FORM A QUESTION:

49

. TOPIC:

192003

-KNOWLEDGE:

Kl.07 QIDs.

NEW Which one of the following percentages of fuel undergoing fission inTa. reactor will result in the largest reactor core effective delayed neutron fraction?

U-235 U-238 Pu-239 A.

90%

7%

3%

B.

80%

6%

14%

C.

-70's 7%

23%

D.

50%

St 34%

4 ANSWER:

A.

QUESTION:

50 TOPIC:

192004 KNOWLEDGE:

Kl.03 QID:

P251 Under which one of the following condit c?s is a reactor core most likely to have a positive moderator iexperature coefficient?

4.

A.

High coolant temperature at beginning-of-life

.B.

High coolant temperature at end-of-life C.

_ Low coolant temperature at beginning-of-life D.

Low coolant temperature at end-of-life ANSWER:

C...

USNRC QE3RRIC FUNDAMErJALS EXAMINATION OCTOBER 1997 PWR - FORM-A QUESTION:

51 -~

TOPIC:-

192004 KNOWLEDGE:

Kl.05 QID:

P1650 (Rev)

Which one of the following' pairs of isotopes is responsible for the negative reactivity associated with a fuel temperature increase near the end of core life' A.

U-235.and Pu-239 B.

U-235 and Pu-240

.C.

U-238 and Pu-239 D.

U-238 and Pu-240 ANSWER:-D.

QUESTION:

52 TOPIC:

192004 KNOWLEDGE:

K1.07 QID:

P1951 A reactor is operating at 70% power.

Which one of the following will directly result in a less negative fuel temperature coefficient?

(Consider only the effect of the change in each listed parameter.)

A.

Increase in fuel temperature B.

Increase in moderator temperature C.

Increase in moderator voids

-D.

Increase in Pu-240 inventory in the core ANSWER:

A. -

~.

... ~.. -.

-. -.~

e.

UMDLC GENERIC FUNDAMENTAL 8' EXAMINATION OCTO ER 1997 PWR - FORM A-4 QUESTION:

53 TOPIC:

192004

~

KNOWLEDGE:

Kl.11-QID:.

P351-The amount of boric acid required to increase the coolant. boron concentration by 50 ppm at BOL conditions (1200 ppm)_is approximately as the amount of-boric acid required to increase boron concentration by 50 ppm at EOL (100 ppm).

A.

the same B.

four times as large C.

eight times'as large D,

twelve times as large ANSWER:

A.

QUESTION:

54 TOPIC:

192005 KNOWLEDGE:

K1.07 QID:

P2156 (Rev)

Which one of the following events will cause control rod worth to decrease?

A.

Fuel. temperature decreases-as the fuel pellets come into coacact with the fuel clad.

B.

RCS boron concentration increases by 5 ppm at 80% power with no rod motion.

C.

Reactor power is decreased from 100% to 90% with no rod motion.

D.

Early in core life, the-concentration-of burnable poison decreases.

ANOWEP: B.

- 40~~

' USMRC GENERIC FUNDMEENTALS EXAMINATION OCTOBER 1997 PWR - FORM A=

QUESTION:

- 55 TOPIC:~

=192005 KNOWLEDGE:

K1. 05 -

QID

P1471- (Rev)'

-The reactor 31s operating at steady state'70% power with the

[

-following=conditionsi RCS boron concentration:

600 ppm Control rod position:

110 inches RCSl average temperature:. 575'F_

Reactor power-is increased to 100% over the next four hours..The q

100% reactor--power conditions are as follows:

RCS boron concentration:

590 ppm Control rod. position:

130 inches RCS average temperature:

580*F Given the following reactivity coefficient / worth values, and neglecting fission product poison reactivity changes, what is the

. differential control rod worth?

Power coefficient:-

-0.3% AK/K/%

Moderator temperature-coefficient:

-0.2% AK/K/"F Differential-boron worth:

-0.1% AK/K/ ppm A.

0.2% AK/K/ inch B.

0.25% aK/K/ inch C.

0.4% AK/K/ inch D.

0.5% AK/K/ inch ANSWER: C.

PROOF pm = 30 x -0.3 = -9.0% Ak/k p, = 1-10 x -0.1 = +1. 0% ak/k pg + p, =

-9. 0 + 1. 0 = -8. 0% Ak/k CRW = p added/ inches = +8.0/20 = +0 4% ok/k/ inch..

.USNRC GENERIC FUNDANENTAL8'EXANINATION OCTOBER 1997 PNR

-FORN A QUESTION:

56 TOPIC:

-192005 KNOWLEDGE:

Kl'.10

-QID:

P455 Which one of the-following describes why.most of the power.is produced in"the lower half of a core that has been operating at 100% power for several weeks at the beginning of. core life?

A.

. Xenon concentration is lower in the lower half of the core.

B.

The moderator to fuel ratio is lower in the lower half of the core.

C.

The' fuel' leading in the lower half of the core contains a higher U-235 enrichment.

D.

The moderator temperature coefficient of reactivity is adding less n,ga ive reactivity in the lower half of the core.

ANSWER:

D.

Q'JESTION.

57 TOPIC:

192005 KNOWLEDGE:

K1.16 QID:

P1657 (Rev)

A reactor is: operating at 85% power with all control rods fully withdraum.

Assuming reactor power does not change, which one of the followit.g-compares the effects of partially inserting (50%)

a single center control rod to the effects of dropping-(full insertion) the same control rod?

A.

A certially inserted rod causes a smaller change in axial power distribution.

B.

A partially inserted rod causes a smaller change in radial power distribution.

C.-

A partially inserted rod causes a greater change in shutdown margin.

D.

A partially inserted rod causes a smaller cha.ge in shutdown margin.

-ANSWER

B.,. _ _

y t

USNRC GENERIC ~ FUNDAMENTALS EXAMINATION' l

OCTOBER 1997 PNR - FORM A 9-QUESTION:.

-58:

TOPIC:

192006

-KHOWLEDGE:

Kl. 0 6 '

QID:

.P2060 A reactor is initially operating at'50% power with equilibrium core xenon-135.

Power-isLincreased to 100% over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period =

and average 1 reactor coolant temperature is adjuated to 588'F using manual rod control.

Rod control is left in Manual and no subsequent operator actions are taken.

s Considering only the reactivity effects of core xenon-135 changes, which one of the following describes the average reactor coolant temperature 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the power change?

A.

Greater than 588'F and decreaaing slowly

-D.

Greater than 588'F and increasing slowly C.

Less-than 588'F and decreasing slowly D.

Less than 588'F and increasing slowly ANSWER:

A.

QUESTION:

59 TOPIC:

19200G KNOWLEDGE:

K1.07 QID:

P1561 Which one_of the following reactor prescram conditions requires the least amount of control rod withdrawal to attain reactor criticality during peak core xenon conditions after.a reactor scram from equilibrium core xenon conditions?

A.

Beginning of core life (BOL) and 100% power B.

End of core life (EOL) and 100% power C.

BOL and.20% power-D.

EOL and 20% power-ANSWER:

C.

.USNRC-GENERIC FUNDAMENTALS EXAMINATION OCTOBER 2.997 PWR - FORM A L UESTION-6;0 Q

TOPIC:

192006 KNOWLEDGE:

K1.09 QID:

P561 (Rev)-

A reactor is initially shut down with nc xenon in'the core.

The reactor.is brought critical and.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months later power-level is at-the point of adding heat.

The shift supervisor has-directed that power be maintained constant at this level for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for testing.

To accomplish this, control rods will have to be:

A.

withdrawn periodically for the duration of the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .-

B.

inserted periodically ~for the duration ~of the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

C..

withdrawn periodically for 4 to 6 hears, then inserted periodically.

D.

inserted periodically for 4 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , then withdrawn periodically.

ANSWER:

A.

QUESTION:

61 TOPIC:

192006 KNOWLEDGE:

Kl.11 QID:

P659 (Rev)

A reactor has been operating at steady-state 50% power for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following a one-hour' power reduction from steady-state 100%

power.

Which one of the following describes the current core xenon-135 concentration?

A.

Increasing toward a peak B.

Decreasing toward an upturn C.

Increasing toward equilibrium

'D.

Decreasing toward equilibrium ANSWER:

D. _

USNRC GENEkIC FUNDAMEdTALS EXAMINATION OCTOBER 1997-PNR - FORN A a

QUESTION: ~

62 TOPIC:

192006 KNOWLEDGE:

Kl.12

_QID:1 P1063 (Rev)

Eighteen hours after_a reactor trip from 100% power, equilibrium xenon conditio;.s,'the-amount of core xenon wi]' ' '-

A.

lower than 100% equilibrium xenon, and will have added a net-positive reactivity since the trip.

B.

lower than 100% equilibrium xenon,'and will have added a net negative reactivity since the trip.

C.

higher-than 100% equilibrium. xenon, and will have added a net positive reactivity since the trip.

D.

higher than 100% equilibrium xenon, and will have added a net-negative reactivity since the trip.

ANSWER:

D.

QUESTION:

63 TOPIC:

192006 KNOWLEDGE:

Kl.14 QID:

P1762 A reactor startup is being conducted and criticality has been achieved 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months after a reactor scram from long term operation at full power-After 1 additional hour, reactor power is stabilized at 10-'% power and all control rod motion is stopped.

Which one of the following describes the response of reactor power over the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months without any further operator actions?

A.

. Power increases toward the point of adding heat due to the decay of Xe-135.

B.

Power increases toward the point of adding heat due to the

-decay of Sm-149.

C.

-Power decreases toward the shutdown neutron level due.to the buildup of-Xe-135.

D.

Power decreases toward the shutdown neutron level due to the buildup of Sm-149.

\\

ANSWER:

A. )

~.

USNRC GENERIC FUNDAMENTAL 5 EIANIMATION OCTOBER'1997 PWR - FORM A QUESTION:.

64 TOPIC:

192007 KNOWLEDGE:

Kl.05 QID ~-

P1964-Which one of the'following compares the rate at-which reactor-power can be increased at the beginning:of core life (BOL) to *.he end of-core' life-(EOL)?

_A.

Faster at EOL due to faster changes in boron concentration B.

Faster at EOL due to greater control rod worth C.

Faster at BOL due to faster changes in boron concentration D.

Faster at BOL due to' greater control rod worth ANSWER:. C.~

USMRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A

. QUESTION:,

!65:

._ TOPIC:

192008 KNOWLEDGE:

'K1.04-

- QID:'-

P1972.(Rev)-

During a reactor startup,-source range indication is stable at 100 cps with K.rr' at 0.95.

.After a number.of rods have been

-withdrawn, source range-indication-stabilizes at 270 cps.

Which one of the following is - the new K.rs?,

A..

0.936'

- B.

0.972 C.- -0.981 D.

0.990 ANSWER: 'C.

PROOF:

CR (1-K ) = CR2 (1-K )

3 3

2 CRa/CR2 (1-K ) / (1-K )

=

3 2

- 270/100 = 0.05/1-K.

2 1-K = 0.05/2.7 2

K = 1-0. 0185 -

2 Ka = 0. 9 814 8 r

4 4

- 47

t-USNRC GENERIC FUNDMEENTALS EXAMINATION OCTOBER 1997 PWR - FORN,A

+-

QUESTION:'

15 6 TOPIC:

192008 KNOWLEDGE:

K1.07-QID:

-P1666

' An estimated critical, rod position (ECP) has been calculated for a reactor startup to be-performed 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months after a reactor trip that ended three months-operation-at 100% power.

Which one of.the'fc11owing conditions will result in criticality occurring-at a lower than estimated critical rod position?

A. : Adjusting reactor coolant system boron concentration to 50 ppm higher than assumed for startup calculations D.

1 malfunction resulting in control rod speed being slower than normal speed

'C.-

Moving the time of startup from 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following the trip D.

Using a pretrip reactor power of 90% to determine power defect ANSWER:

D.

QUESTION:

67 TOPIC:

192008 KNOWLEDGE:

Kl.09 QID:-

P68 (Rev)

When a reactor is exactly critical, reactivity is:

A.

infinity.

B.

undefined.

C.

0.0 AK/K.

D.

-1.0 AK/K.

ANSWER:

-C.

1 3

USNRC GENERIC FUNDMG3fTALS EXAMINATION :

?

OCTOEER 1997 PNR

= FORM A G;'ESTION:

68

-TOPIC:

192008 KNOWLEDGE:

K1,10 QID:.

P1567 With-a reactor on'a constant period of 30 minutes, which one of-the following power changes requires the'least' time to occur?

A.-

1%' power to 6% power B.

10% power to 2'J% power C.

-20%' power-to 35% power D.

40% power to 60% power ANSWER:

D.

PROOF:

Pg = Poe"'

tln Pr/P

= t o

in 6/1(30) = 1.79 (30) = t = 53.7 minutes in 20/10(30)

.693(30)

=t = 20.8 minutes

=

in 35/20(30)

.56(30) = t = 16.8 minutes

=

in 60/40(30)

.41(30) = t = 12.3 minutes

=

49 -

]

l 3

USHRC annemIC FUNDAMBIPPALS RXAMINATIOtt OCTosER 1997 FWR - FORM A QUESTION:

69 TOPIC:

192008 f

KNOWLEDGE:

Kl.14 QID:

P972 (Rev) l A reactor is critical at the point of' adding heat (POAH) when a l

small amount of negative reactivity is added to the core.

If the same amount of positive reactivity is added to the core-approximately 5 minutes later, reactor power Will A.

increase and stabilize at the POAH.

B.

quickly stabilize at a power level below the.POAH.

C.

continue to decrease on a negative 80 second period until the shutdown equilibrium neutron level is reached.

'D.

continue to decrease with an unknown period until the shutdown equilibrium neutron level is reached.

ANSWER:

B.

QUESTION:

70 TOPIC:

192008 KNOWLEDGP, Kl.21 OlD:

P1370 A reactor has been operating at 80%-power for several weeks.

A partit steam line break occurs and 2% total steam flow is escapi..g.

Turbine load and control rod position remain the same.

Assuming no operator or automatic actions, when the plant stabilizus, reactor power will be and average l

reactor coolant temperature will be T.

highet; higher B.. uncha.noed; higher

C.

higher lover D[ vachanged;~ lower ANSWER:-

C.

i

.l.

1

... _. - ~ -

3 USINic GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PWR - FORN A j

+p, QUESTION:

.71 TOPIC 192008 KNOWLEDGE:

K1.26 QIDi ~

P370 After one month of operation at 100% reactor power, the fraction of thermal power beir.9 produced from the. decay of fission products in the operating reactor ist A.

greater than 10%.

B.

greater than 5% but less than 10%i C.

greater than 1% but less than 5%.

D.

lees than 1%.

' ANSWER:

B.

i 4

1 QUESTION:

72 TOPIC:

192008 KNOWLEDGE:

Kl.27 QID:

P1672 (Rev)

A reactor is operating at 100% power near the end of core life.

The greatest contribution to col. heat production is being provided by the fission of A.

U-235 and U-238.

B.

U-235 and Pu-239.

C.

U-238 and Pu-239.

D.

U-238 and Pu-241.

ANSWER: B.

i p

51 -

..e-

,i.,.

3,

..-y

,..,,-.,.w, ymm,. -,.

...-w--3 w w. r

.,,,. ~

. _. ~

USNRC GENERIC FUNDAMENTALS EXANINATIOIf I

OCTOBER 1997 PNR - FORN A QUESTION:

73 TOPIC:

193001 I

KNOWLEDGE:

K1.01-f QID:

P2073 (Rev)

Which one of the following-is arranged from the highest pressure i

to the lowest pressure?

A.

2 psig, 12 inches Hg absolute, 8' psia B.

2 psig, 18 inches Hg absolute, 8 psia C.

12 psia, 20 inches Hg absolute, 2 psig D.

12 psia, 30 inches Hg absolute, 2 psig t

' ANSWER:

B.

J PROOF A. is equivalent to 17 psia, 6 psia, 8 psia B. is_ equivalent to 17 psia, 9 psia, 8 psia C. is equivalent to 12 psia, 10 psia, 17 psia D.-is equivalent to 12 psia, 15 psia, 17 pain i

QUESTION:

74 TOPIC:

193003 KNOWLEDGE:

K1.14 QID:

P1674 A reactor trip occurred 10 minutes ago due to a loss of coolant accident.

Emergency. coolant injection is in progress and pressurizer level is increasing.

Current pressurizer conditions are as follows:

Pressurizer liquid temperature = 540*F Pressurizer vapor temperature

= 607'F Pressurizer pressure

= 1410 psia Pressurizer level

= 60%

Given these conditions, the pressurizer liquid is and the pressurizer vapor is A.

saturated; saturated i

D.

saturated;Lsuperheated i

C.

-subcooled; saturated D.. subcooled;'superheated P

ANSWER:

D.

o-3 USHRC GENERIC FUNDMEENTALS EXAttI3tATION OCTOBER 1997 PNR - FORN A QUESTION:

75 l

TOPIC:

193003 KNOWLEDGE:

K1.25 QID:

NEW f

i 1 x 10' lbm/hr saturated steam at 30% steam quality is leaving a i

main turbine and entering a condenser at 2. 0 psia.

Condensate is entering the hotwell at 118 degrees F.

j Which one of the following-is the approximate condenser heat

[

transfer rate?

A.

3.1 x 10' Btu /hr B,

5.8 x 10' Btu /hr C.

7.2 x 10' Btu /hr D.- 9.9 x 10' Btu /hr ANSWER:

A.

PROOF From steam tables:

Exhaust steam enthalpy is 1116.1 -

(0.7)(1022.2) = 400.56 Btu /lbm From steam tables:

Condensate enthalpy is 86 Btu /lbm O = m-dot delta-h 0 =-(1,000,000 lbm/hr)(400.6 - 86 Btu /lbm) i 0 = 314,600,000 Btu /hr QUESTION:

76 I

TOPIC:

193004 KNOWLEDGE:

K1.11 OID:

P1176 (Rev)

The thermodynamic cycle efficiency of a power plant will increase if:

A.

the amo: at of condensate depression is decreased.

B.

a high-pressure feed water heater is removed from service.

j C.

condenser vacuum decreases from 29 inches to 25 inches.

D.-

power is decreased from 100% to 25%.

ANSWER:-

A.

t

- S3 -

i

3 USMRC GENERIC FUNDMEENTALS EXAMINATION PCf0BER 1997 FWR - FORM A-QUESTION:

77 TOPIC 193004 KNOWLEDGE:

Kl.15 QID:

P1277 A heatup and pressurization of the reactor coolant system (RCS) is in progress following a-maintenance shutdown..RCS pressure is 800 psia with a steam bubble in the pressurizer.

Pressurizer power-operated relief valve (PORV) tailpipe temperature has been steadily rising.

Assume 97.5% quality saturated steam in the pressurizer vapor space, PORV downstream pressure is 30 psia, and PORV leakage is an ideal throttling process.

Which one of the following is the expected PORV tailpipe

' amperature if a PORV is leaking by?

A.

264*F D.

284*F C.

302*F D.

322*F ANSWER:

D.

QUESTION:

78 TOPIC:

193005 KNOWLEDGE:

Kl.03 QID:

P277 (Rev)

If the moisture content of the steam supplied to a main turbine increases, turbine work will:

A.

decrease because the enthalpy of the steam being supplied to the' turbine has decreased.

D.

decrease becauso moist steam results in more windage losses in the turbine.

C.

. increase because the enthalpy of the steam being supplied ~to

-the turbine has. increased.

- D.

increase because moist steam results in less windago losses in the-turbine'.

ANSWER: A. i J.__,_..-,_...-._,.._....

_,,._.._,_-,i_....,,_.

'o y

US85tc GEIIERIC marmyAL3 EXAMINATION-OCTOBER 1997-PWR - FORM A

_ QUESTION:

79 TOPIC 193006 KNOWLEDGE:

Kl.04 QID:

P78 (Rev)

Which-one of the following operating practices minimizes the

- possibility of teater hammer?

A.

Change valve positions as rapidly as passible.

B.

Start centrifugal pumps with the discharge valve throttled.

C.

Start positive-displacement pumps with the discharge valve closed.

D.

Vent systems only after initiating system flow.

-ANSWER:

B.

-QUESTION:

80 TOPIC:

193006 KNOWLEDGE:

K1.05 QID:

P1986 A 47 gpm leak has developed in a cooling water system that is operating at 150 psig.

Which one of the following will be the leak rate when system pressure has decreased to 75 psig?

A.

23.5 gpm B.-

33.2 gpm C.

36.5 gpm D.

37.3 gpm-ANSWERr B.

PROOF:

-DP =-fa DP /DP, = (f /f:)*

3 3

1.414 = 47/f f: = 47/1.414 f = 33.2 gpm

- SS -

USNRC rantammIC FUNDhMENTALS EXAMINATION OCTOBER 1997 FMR - FORN A QUESTION:

81 TOPIC:

193006 KNOWLEDGE:

K1.11 QID:

P1502.

Refer to the drawing of a, cooling water system in which only pump A is operating and the pump discharge valve is currently 50% open (see figure below).

If pump A is cavitating, which one of the following will reduce or eliminate cavitation in pump A?

A.

Starting pump B-B.

Positioning the discharge valve to 75% open C.

Raising the water level in the surge tank by 2 feet D.

Decreasing heat exchanger service water flow rate by 10%

ANSWER:

C.

P i.T nsb g,=

we

%W v

N. O MWP A C00UNG WATER SYSTEM 56.--

3 USNRC GENERIC FUNDAMENTALS EXAMINATIOtt OCTOBER 1997 PNR - FORN A QUESTION:

82 TOPIC:

193006 KNOWLEDGE:

K1.15 QID:

NEW Water at 90 degrees F and 50 psig is flowing ~through a 10-inch diameter pipe at 100 lbm/sec.

The pipe then splits into two pipes, a 4-inch diameter pipe and an'8-inch diameter pipe.

Disregarding any flow restrictions other than pipe size, which one of the following lists the approximate flow rates through the inch and 8-inch diameter pioes?

4-inch Pipe-8-inch _ Pipe

_(1bm/sec)

(1bm/sec)

A.

20 80 D.

25 75 C.

30 70 D.

33 67 ANSWER:

A.

PROOF m = PAv ml + m2 = 100 pAlv + pA2v = 100 pv(Al +A2) = 100 pv(80) = 100 pv ='100/80 ml = pvAl ml = 100/80 (16) ml = 1600/80 4 20 lbm/see m2 = pvA2-m2 = 100/80 (64) ml = 6400/80 = 80 lbm/sec p.

USNRC GENERIC FUNDhMENTALS EXAMINATION OCTOBER 1997 PNR - FORN A QUESTION:

83 TOPIC:

193006 KNOWLEDGE:

Kl.15 OID:

P1282 Two centrifugal pumps and two positive displacement pumps are able to be cross connected to provide flow in a system.

Each pump will produce 100 gpm at 1000 psig discharge pressure and each pump has a design maximum pressure of 1500 psig.

If system pressure is 1200 psig, which one of the following will j

produce the greatest system flow rate?

A.

Two positive displacement pumps in series D.

Two positive displacement pumps in parallel C.

Two centrifugal pumps in series D.

Two' centrifugal pumps in parallel ANSWER:

B.

QUESTION:

84 TOPIC:

193007 KNOWLEDGE:

Kl.01 QID:

NEW Which one of the following describes a heat transfer process in which convection is the most significant heat transfer mechanism?

A.

From the reactor fuel to the core barrel during core uncovery B.

Through the tube walls in a steam generator during normal ope. ration at 100% power C.

From the reactor fuel to the steam generators during a station blackout-D.

From fuel pellet centerline to fuel clad during normal operation at-100% power ANSWER:-

C.

('

~

USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 FWR - FORM A QUESTION:

85 TOPIC:

193007 KNOWLEDGE:

K1.06 QID:

P384 The power rango nuclear instruments have been adjusted to 100%

based on a calculated calorimetric (secondary heat balance).

Which one of the following will result in actual reactor power being less than indicated reactor power?

A.

The feedwater temperature used in the calorimetric calculation is higher than actual.feedwater temperature.

B.

The reactor coolant pump heat input term is omitted from the i

calorimetric calculation.

l C.

The feedwater flow rate used in the calorimetric calculation is lower than actual feedwater flow rate.

D.

The steam pressure-used in the calorimetric calculation is higher than actual steam pressure.

i ANSWER:

B.

i 3

b

..-..-.-..-.-..w....

_ _....., _ ~

USNRC GElmRIC FtnmhttElfTALS EXAttIalATI0tt OCTOBER 1997 PWR - FOR88 A 1

QUESTION:

86 TOPIC:

193008 KNOWLEDGE:

K1.01 OID:

-P1286 l

t Refer to the drawing of a pool boiling curve-(see figure below).

l Which region of the curve contains the operating point at which the hottest locations of the reactor operate to transfer heat

-from the cladding to the coolant at 100% power?

A.

Region I I

B.

Region II C.

Region III j

D.

Region IV l

ANSWER:

B.

I 11 111 IV i

l LOG HEAT FLUX LOGAT POOL BOluNG CURVE F

b

'i -_

l,

p i..--.

--.u.z-..~.-,

~.

3 USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PNR - FORN A QUESTION:

87 TOPIC -

193008 KNOWLEDGE:

Kl.03 l

QID:

P487 (Rev)

Which one of the following describes why the core heat transfer rate increases when nucleate boiling begins on the surface of a fuel rod?.

A.

Steam has a greater thermal conductivity than water.

B.

The formation of steam bubbles increases coolant flow rate along the fuel rod.

3 C.

Radiative heat transfer begins to supplement convective heat transfer.

D.

Heat transfer by steam bubble formation is more effective than through a liquid film.

ANSWER:

D.

QUESTION:

88 TOPIC:

193008 KNOWLEDGE:

Kl.05 QID:

P1889 (Rev)

A plant'is operating with the following initial conditions:

Reactor power is 55% in the middle of a fuel cycle.

Axial and radial power distributions are peaked in the center of the core.

Which one of the following will decrease the steady-state departure from. nucleate boiling ratio?

A.

A reactor trip occurs and one control rod remains fully withdrawn from the core.

B.

A presrarizer malfunction increases reactor coolant system pressure by 20 psig.

C.

The operator increases reactor coolant boron concentration by 5 ppm with no rod motion.

D. - Core.Xe-135 depletes =in-proportion to the axial and radial power distribution with no rod motion.

--ANSWER:

D.

61 -

t t

4 p s, y.,,

-w

,v.-,-r.--,c,,,-

y r

.,,,,-,w,-,-

.,w y

h-y,-

1-5,,y,my,.

,yw---,

,,v-----y

,,-'rr--w-cT

i USMRC GENERIC FUNDhMENTALS EXAMINATION OCTOBER 1997 PWR - FORM A QUESTION:

89 TOPIC:

193008 KNOWLEDGE:

Kl'.07~

QID:

- P1689-(Rev)

Refer to the drawing of a pool-boiling curve (see figure below).

The point at which heat flux stops-increasing and the critical heat flux has been reached (point B), marks the-beginning of:

A.

nucleate boiling.

i B.

stable film boiling.

C.- - partial film boiling.

D.

single-phase convection.

ANSWER:

C.

i i

i 8

O LOG HEAT Flux

~

l LOG AT POOL BoluNG CURVE

- 62:-

t

-+

we-e e

3 w-ip T

M

-wye

-,y-+

1l-

--w1---

t -r y +-

y v

-USNRC ra - IC FUNDAMENTALS EXAMINATION OCTOBER 1997 FNR - FORM A QUESTION:

90 TOPIC:

193008 KNOWLEDGE:

K1.10 QID -

P990 A reactor is operating at 100% steady-state power at the end of core life with all control rods fully withdrawn.

At what axial location in a typical fuel assembly will the minimum departure from nucleate boiling ratio occur?

A.

At the bottom of.the fuel. assembly B.

At the top of the_ fuel assembly-C.

Between the-bottom and the midplane of the fuel assembly D.

Between the-midplane and the top of the fuel assembly ANSWER:

D.

4 QUESTION:

91 TOPIC:

193008 KNOWLEDGE:

Kl.19 QID:

P1886 (Rev)

A reactor is producing 3400 MW of thermal output. with a vessel AT of 60*F and a vessel mass flow rate of 1.1 x 108 lbm/hr.

If core

'AT is 63.6*F, what is core bypass flow rate?

(Assume bypass flow AT equals 0'F.)

A.

5.66 x 10' lbm/hr B.

6.23 x 10' lbm/hr -

C.

5.66 x 10' lbm/hr D.

6.23 x 10' lbm/hr ANSWER:

B.-... - - - -.

=

USSIRC GENERIC FUltDAttElffALS EXAbtI8tATION OCTOBER 1997 PWR - POR88 A PROOP:

i D=ricpAT igcp AT, igcp AT, 4 %cpAT, f

AT' 60 '

f

1. I x 10' #/ hr

( = ig

=

AT, 63.6<

i 4 = 1,1(. 9434) x 10' #/ hr = 1. 038 x 10 #/ hr 8

4"4+%

%A-4 t

= ( l.1 - 1. 038) x 10' #/ hr

= 0. 0623 x 10' #/ hr

= 6. 23 x 10' #/ hr i

t

! T w

r-

.c-e

.,c-n-s,,

.n, '.

,-.e2----

r.-yr-r..--.~

-ag v v,

.~

-.--,-e~-wm,'-

-, - - - - - p

i g-.

USNR/, GENERIC FUNDAMENTALS EIANIMATIOtt OCTOBER 1997 FMR - PORN 4 QUESTION:

92 TOPIC:

193008 KNOWLEDGE:

X1.23 QID:

P1591-A reactor had been operating at a constant power level for the last two weeks when a loss of all ac power occurred, thereby causing a scram and a loss of forced reactor coolant flow.

Natural circulation reactor coolant flow developed and stabilized

(

30 minutes after the scram, t

Which one of the following combinations of initial reactor power

[

and. post-scram steam generator pressure will result in the highest stable natural circulation flow rate 30 minutes after the scram?

INITIAL POST-SCRAM REACTOR STEAM CENERATOR T20WER PRESSURE A.

100%

1100 paia B.

100%

1000 psia I

C.-

25%

1100 psia D.

25%

1000 pala i

ANSWER: D.

i f

' 1 t

?

5 t

h ss -

~-

...,-,,-,-,--,-n,,,,,,,..,n,

,,-.a..,

,.e

-n,

-n.-

'e y

USNRC GENERIC FUNDAMENTALS EXAMINATIC48 OCTOBER 1997 PNR - PORN A QUESTION:

93 TOPIC:

193008 KNOWLEDGE:

Kl.25 QID:

P793 A reactor coolant system natural circulation cooldown is in progress via the steam generator (S/0) atmospheric steam relief valves (operated in manual control).

If high point voiding interrupts natural circulation, which one of the following will occur?

(Assume feed flow rate, relief valve position, and decay heat level are constant.)

A.

S/O level decreases and core exit thermocouple (CETC) indication increases, D.

S/G_ level decreases and CETC indication decreases.

C.

S/G level increases and CETC indication increases.

D.

S/G-level increases and CETO indication decreases.

ANSWER:

C.

- F

e UsantC GENERIC FtnIDA8ERINTALS EXAMISEATIOtt OCTOBER 1997 MfR - FORA 8 A QUESTION:

94 TOPIC:

193009 KNOWLEDGE:

Kl.02 QID:

P1195 A reactor is operating at 80% power at the beginning of a fuel cycle.

All control rods are fully withdrawn and in manual control.

Moderator temperature coefficient is negative.

Which one of the following will decrease the axial peaking (or hot channel) factor?

(Assume no subsequent operator action is taken and that turbine load and xenon distribution do not change unless stated.)

A.

One bank of control rods is inserted 10%.

B.

One control rod fully inserts into the core.

C.-

Turbine load / reactor power is reduced by 20$.

D.

Reactor coolant system boron concentration is reduced by 50 ppm.

l ANSWER:

C.

QUESTION:

95 TOPIC:-

193010 KNOWLEDGE:

Kl.01 QID:

P1896 (Rev)

Brittle _ fracture of the reactor vessel (RV) is least likely to occur during a of the RV when RV temperature is the reference temperature for nil-ductility transition (RTmy).

A.

cooldown; above B.

heatup; above C.

cooldown; below D.

heatup; belots ANSWER:

B.

. 67--

'e o

y USNRC OENERIC W h W ALS EXAMINATION OCTOBER 1997 PNR - FORT! A QUESTION:

96 TOPIC:

193009 KNOWLEDGE:

Kl.07 QID:

P1594 (Rev)

Refer to the drawing of a fuel rod and coolant flow channel at the beginning of core life (see figure below).

Given the following initial core parameters:

Reactor power 60%

=

T

..t 560'F-

=

Tru s cent.run.

2500*F

=

Which one of the following will be he fuel centerline temperature at the end of core life..f the total fuel-to-coolant thermal conductivity doubles?

(Assume reactor power is constant.)

A.

1080*F B.

1250*F C.

1530*F D.

1810'F ANSWER:

C.

CLAD PUCL PELLET v

v COOLANT COOLANT FLOW

%s PLOW FUEL ROD AND COOLANT FLOW CHANNEL -

68 -

a-s usaNtc GENERIC FU3fDhttENTALS ' EXAttTMATIOtt OCTOBER 1997 FWR - FORat A PROOF AT/2 = (2500 - 560)/2 T,, = T. + AT = 5 6 0 + 9 7 0 -

= 1940/2 T,, = 153 0 *F

= 970*F 4

k 4,

USNRC GENERIC FUNDAMENTALS EXAMINA? ION OCTOBER 1997 PWR - FORN A

. QUESTION:

17 TOPIC:

93010 KNOWLEDGE:

Kl.01 QID:

P1296 Which one of.the following increases the probability of brittle fracture _of a pressure vessel wall?

J A.

A high tempert 're rather than a low temperature B.

A tensile stress rather than a compressive stress C.

Performing a 100'F/ hour heatup rather than a 100'F/ hour CooldoWn D.

Using materials fabricated from stainless steel rather thau carbon steel ANSWER:

B.

QUESTION:

98 TOPIC:

193010 KNOWLEDGE:

Kl.05 QID P2098 (Rev)

Two identical reactors have been in operation for the last 10 years. Reactor A has experienced 40 heatup/cooldown cycles and has an average power capacity of 50%.

Reactor B has experienced 30 heatup/cooldown cycles and has an average power capacity of 60%.

t Which reactor will have the highest reactor-vessel nil-ductility i

transition temperature?

- A.

Reactor A due to the greater number of heatup/cooldown cycles B.

Reactor A due to the lower average power capacity

. C.

Reactor B due to the. fewer number of heatup/cooldown cycles D.

Reactor B due to the higher average power capacity ANSWER:

D.

i t

,.m.m.-

_,m._._

,s.,

USMRC rammemIC FUNDAMENTALS EXAMINATION OCTOBER 1997 PNR - FORM A QUESTION:

99-TOPIC:

193010 KNOWLEDGE:

Kl.06 QID:

.P99 A plant is shut down with the reactor coolant system at 1200 psia and 350*F.

Which one of the following would be most likely to cause pressurized thermal shock of the reactor vessel?

A.

A rapid depressurization followed by a rapid heatup

.- B.

A rapid depressurization followed by a rapid cooldown C.

A rapid cooldown followed by a rapid pressurization C.

A1 rapid heatup followed by a rapid pressurization ANSWER:

C.

QUESTION:

100 TOPIC:

193010 KNOWLEDGE:

Kl.07 QID:

P1199 During cooldown, the thermal stress on the reactor vessel is:

A.

tensile across the entire wall.

D.

compressive across the entire wall.

C.

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

D.

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

ANSWER:

C.

t

~.

000 FINAL ANSWER KEY 000 OCTOBER 1997 NRC GENERIC FUNDAMENTALS EXAMINATION PRESSURIZED WATER REACTOR - ANSWER KEY FORM ANS FORM ANS FORM ANS FORM ANS A

B A

B 1

29 B

26 54 D

51 79 D

76 4

A 2

30 D

27 55 A

52 80 A

77 5

B 3

31 B

28 56 A

53 81 A

78 6

A 4

32 C

29 57 C

54 82 B

79 7

B 5

33 D

30 58 A

55 83 C

80 8

B 6

34 A

31 59 A

56 84 D

81 9

C 7

35 A

32 60 D

57 85 B

82 10 A

8 36 A

33 61 D

58 86 A

83 11 B

9 37 B

34 62 D

59 87 C

84 12 C

10 38 A

35 63 B

60 88 A

85 13 B

11 39 A

36 64 B

61 89 D

86 14 B

12 40 C

37 65 C

62 90 D

87 15 D

13 41 D

38 66 C

63 91 A

88 16 D

14 42 D

39 67 C

64 92 C

89 17 C

15 43 A

40 68 D

65 93 C

90 18 D

16 44 A

41 69 A

66 94 D

91 19 B

17 45 B

42 70 B

67 95 C

92 20 B

18 46 D

43 71 A

68 96 D

93 21 C

19 47 B

44 72 D

69 97 8

94 22 C

20 48 B

45 73 D

70 98 C

95 23 B

21 49 D

46 74 A

71 99 B

96 24 C

22 50 D

47 75 C

72 100 B

97 25 B

23 51 B

48 76 A

73 1

B 98 26 D

24 52 B

49 77 A

74 2

D 99 27 C

25 53 C

50 78 C

75 3

A 100 28 C

]

3

.6 UNITED STATES NUCLEAR REGULATORY CONNISSION BOILING WATER REACTOR GENERIC FUNDAMENTALS EXANIMATION OCTOBER 1997 - FORN A September 17, 1997 Please Print i

Names Facility:

Docket No.:

Start Timer-Stop Times INSTRUCTIONS TO APPLICANT Answer all the test items using the answer sheet provided.

Each item has equal point value.

A score of at least 80% is required to pass this portion of the written licensing examination.

All examination papers will be collected 3.0 hours0 days 0 hours 0 weeks 0 months after the examination starts.

This examination applies to a typical boiling water reactor (BWR) power plant.

SECTION QUESTIONS

% OF TOTAL SCORE COMPONENTS 1 - 44 REACTOR THEORY 45 - 72 THERMODYNAMICS 73 - 100 TOTALS 100 All work done on this examination is my own.

I have neither given nor received aid.

Applicant's Signature

-s s%ss Ann eurosLInns rom Tus o

ON l

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 examination.

2.

Fill in the name of your facility.

3.

Fill _in your individual docket number.

t 4.

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

S.

Two aids are provided for your use during the examinations i

t (1)

An equations and conversions sheet contained within the l

examination copy, and (2) -Steam tables provided by your proctor.

6.

Plade your answers on the sheet provided.

Credit will only be j

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.

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

Cheating could also result in severe penalties.

9.

Restroom trips are limited.

Only ONE examinee may leave the room at a time.

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

10.

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

Turn in your examination materials, answer sheet on top, followed by the examination booklet, then examination aids -

steam table booklets, handouts and scrap paper used during the examination.

12.

After turning in your examination materials, leave the examination area, as defined by the proctor.

If after leaving you are found in the examination area while the examination is

.in proceress, your examination may be forfeited.

!n

s s

GENERIC FUNDAMENTALS EXAMINATION EQUATIONS AND CONVERSIONS HANDOUT SHEET r

EQUATIONS Q = thC AT P = P.10miu p

Q = - thAh P = P e'"O o

r O = UAAT A = A e-At i

D = thy'aicue CRm = S/ (1 - K.rg)

CR (1 - K,rts)

CR (1 - Kerra)

=

t 2

AT =

thu,,, co, 1/M = CR /CRx t

K rt " 1/(1 - P)

DRW = 9'ip/,'y 9

p= (K.tr - 1) /K.tr

^

SUR = 26.06/t m = pAV

_D-p t=

A,,, p W

= thAPu E = IR t*

p-p. -- +

t I+At Eff. = Net Work Out/ Energy In err 8

3 l' = 1 x 10** seconds u ( Pa - P ) + (4 -4) + g(z: -z) =0 3

a A., = 0.1 seconds'1 32.2 lbm-ft/lbf-seca ge =

CONVERSIONS 3.41 x 10' Btu /hr 1 Curio

'l Mw

=

3.7 x 102' dps

=

2.54 x 103 1 hp Btu /hr 1 kg

=

2.21 lbm

=

1 Btu =

778 ft-lbf-1 gal t.,

8.35 lbm

=

C (5/9) (*F - 32)

I f t,...,

8 7.48 gal

=

'F-

- ( 9 / 5) ('C) + 32

=

3-

f.

1 1

USNRC GENERIC FUNDAMENTALS EXAMINATIOst OCTOBER 1997 BNR - FORM A QUESTION:

1

' TOPIC:

291001 KNOWLEDGE:

Kl.01 QID:

B1701 A vertical safety valve has a compressed spring assembly that is applying _1200 lbf to.the top of the valve disk in opposition to system pressure.

System pressure is-being exerted on the underside of the valve disk that is 3 inches in diameter.

-Which one of the following is the approximate system pressure at which the safety valve will open?

(Neglect the effect of atmospheric pressure.)

l A.

44 psi B.

64' psi C.

128 psi D.

170 psi ANSWER:

D.

PROOF:

F = PA P = F/A P = 1200/3.14(1.5)8 P = 1200/7.07 P = 169.7 psi QUESTION:

2 TOPIC:

291001 KNOWLEDGE:

Kl.04 QID:

B1702 Which one of the following statements describes the flow rate characteristics of a typical gate or globe valve?

A.

The last 25% of valve stem movement in the open direction for o gate valve will produce a greater change in flow rate than the first 25% of valve stem movement.

B.-

The'last 25% of valve stem movement in the open direction for a-globa valve will produce a greater change in flow rate than-the first 25% of valve stem movement.

C.-

A globe valve designed specifically for throttling flow must be operated in the first 25% of its range to control flow.

D.

The~first 25% of valve stem movement in the open direction for a-gate valve will produce a greater change in flow rate than the last 25% of valve stem movement.

ANSWER:

D. l

c USNRC GENERIC Ftpmum8TALS EXAMINATrou OCTOBER 1997 BWR - FORM A 1

e QUESTION:

3-TOPIC:

291001-KNOWLEDGE:

Kl.05

-QID:

B1404 Which'one of the following.is a generally accepted method for locally verifying that a manuel valve is fully closed.in a depressurized static piping system?

A.

Check'a downstream flow gauge to be indicating zero flow B.

Visually observe the' valve rising-stem threading to be fully exposed C.

Attempt _to turn the_ valve handwheel in the'close direction and verify no movement D.

Compare an upstream and downstream pressure gauge to ensure zero differential pressure ANSWER:

C.

QUESTION:

4 TOPIC:

291001 ENOWLEDGE:

Kl.07 QID:

B1102 (Rev)

Two common types of check valves used in power plants are:

A.

globe and gate.

B.

ball-and plug.

LC.

swing-and lift.

D.-

needle and angle.

ANSWER:-

C.

i 5-

. ~. -

i USNRC GENERIC FUNDAMENTALS EXAMINATION-OCTOBER 1997 BWR FORM A QUESTION:

5 TOPIC::

E291001 KNOWLEDGE ( Kl.02 lOID:

B2005 (Rev)

When comparing the characteristics of' gate valves _and globe valves

-)

in_an operating system,.-a-globe valve generally has a

-pressure drop when fully open, and is-commonly used for i

throttling system _ flow.-

s' J.-

_ smaller; less

.B.

-larger; more 1

C.

smaller; niore D.

larger; less

~ ANSWER:

~B.

QUESTION:

6 TOPIC :'

291002 KNOWLEDGE:

Kl;01 OID:

B706 (Rev)

A cooling water system is operating at a steady-state flow rate of 7_00 gpm-with 60 paid across the flow transmitter venturi.

If cooling water flow rate is increased to 900 gpm, differentia 1' pressure across the flow transmitter venturi will be:

A, 68.0 paid.

B.

77.1 paid.

C.

99.-2 paid.

D.

127.5 psid'.

ANSWER: C.

-PROOF: _

D/P = Fa.

D/ Pa = ' D/ P (F /F ):

3 3

= 60 (900/700)*

.= 99.2:-

-G-

s ; *.,.

~

USNRC GENERIC FUns m ensTALS EXAMINATION 9

OCTOBER 1997 BWR - FORM'A--

i QUESTION:-

7-(TOPIC:

291002I KNOWLEDGE:

Kl'.04

- QID:-

B.07-I Which one of the following will cause indicated flow rate to be higher thaniactual flow rate uuing a differential pressure flow detector--and a calibrated orifice?

A.

Debris becomes lodged in the orifice.

{

J 4

l B.

A^1eak develops-in the high pressure sensing line C.

The orifice erodes over time.

-D.

The flow-detector equalizing valve is inadvertently opened.

ANSWER:

A.

QUESTION:

8-TOPIC:

291002 KNOWLEDGE:

Kl.12 QID:

B611 Which one of the following parameters requires square root extraction when measured by differential pressure detectors?

A.

Condenser vacuum B.

Reactor vessel level C.

Reactor vessel pressure D.

Recirculation pump flow rate ANSWER:

D.

U

1 b-T. '

k

^

USNRC GENERIC FUNDMEENTALS EXAMINATION OCTOBER-1997 BWR

--FORM A QUESTION:

-9' TOPIC:

291002 KNOWLEDGE:

Kl.05-QID:

B1808 (Rev)

Refer to the drawing of a pipe ~ elbow used for flow measurement in a cooling water system (see figure below).

A differential pressure (D/P) flow detector is connected to instrument lines A and B.

If instrument line A develops a leak, indicated flow rate will due to a measured D/P.

A.

increases larger-B.

increase; smaller C.

decrease; larger

- D.-

decrease; smaller ANSWER:

D.

III B-e 6=

A PIPE ELIMWV 1..- -

USMRC GENERIC-FUNDAMENTALS EXAMINATION OCTOBER 1997=BWR - FORM A i

QUESTION:

10 i

TOPIC:

291002 KNOWLEDGE:

Kl.08 QID:

B1909 (Rev)

Refer to the drawing of a tank differential pressure (D/P) level-detector (see figure below).

The-level detector is oeing used in a level control system that is calibrated to maintain tank level at 80% at the current water temperature of 70*F.

If water temperature gradually. increases and stabilizes at 90'F, the level control system will cause actual tank' level'to:

A.

remain at 80%.

B.

increase and stabilize above 80%.

C.

oscillate around 80%.

D.

decrease and stabilize below 80%.

ANSWER:

B.

TANK OPEN TO ATMOSPHERE r

WATER 4

. DIP DETECToM TANK DIFFERENTIAL PRESSURE LEVEL DETECTOR 9-

'i J..

USHRC GENERIC-FDIEDhbEENTALs armutuaTICII-OCTOBER 1997 BWR - FORat'A-e-

QUESTION:

11-TOPIC:-

c291002

. KNOWLEDGE:--Kl.08

-QID:

-NEW-Refer-to'the drawing'of-a tank with a differential pressure level

~

Ldetector (See figure below.)..

The-level detector was calibrated with reference leg and tank-contents-- temperature: at 70*F.

-An increase in ambient temperature causes.the temperature of the reference leg and tank contents to increase to-110*F.__

With the; temperature of the reference leg and-tank contents' stable-

-at.110*F, current level indication will;be:

A.

-higher.than initial due to reference _ leg spill over.-

-- B. - higher than initial due to expansion-of tank contents, c.

the same as initial due to offsetting density changes in the reference leg and tank contents, D.

the same as initial due to the reference leg being connected to the upper-portion of the tank.

' ANSWER:

A.

6 REFERENCE LEG FILL CONNECTION 1

OR V PRESSURE P

V VW/

EQUA t

v><UZING//

ve-

,A DETECTOR TANK DIFFERENTIAL PRESSURE LEVEL DETECTOR l

.a

.. ~

-~.,

. ~ _

L.

p y

USNRC GENERIC FUNDAMENTALS EXAMINATIO8f OCTOBER-1997 BWR - FORM A' QUESTION:

.12

_ TOPIC.

291002 KNOWLEDGE:

Kl.19 QID:

B1214

-The reactor scrammed due-to a loss-of-coolant accident 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago.

To verify adequate reactor vessel water level, the source range monitors (SRMs) are inserted._ As the SRMs enter the core, count rate begins to increase and then stabilizes.

If the SRMs enter a voided section of the core, count rate will_

suddenly:

-A.

decrease due to decreased fast fission..

B.

decrease due to increased neutron leakage.

C.

~ increase due to increased neutron migrat1'n length.

D.

increase due to decreased moderator neutron absorption.

ANSWER: B.

QUESTION:

13 TOPIC:

291002 KNOWLEDGE:

Kl.24 QID:

NEW An initial. radiation survey is about to be performed in an area of unknown radiation field intensity.

Which one of the following types of radiation monitoring instruments and settings should be used?

A.

A Geiger Mueller survey meter selected to the low range B.

A Geiger Mueller survey meter selected.to the high. range C.

An iott cl:9mber survey-meter selected to the low range D.

An ion chamber survey meter selected to the-high range ANSWER: D. ;

21 W *'

U530tC GENERIC FUunmenyALg EXAMINATION OCTO:ER 1997 BWR --FORM A 1 QUESTION:

14 TOPIC:

291002 KNOWLEDGE:

Kl.21 QID:

B2114

.A gas-filled radiation detector operating in the proportional

, region is exposed-to a constant gamma radiation field.

If the

. applied voltage is increased but maintained within the proportional region, the rate of-ion collection will:

A.

stay approximately the same because-alllof the primary ions were already being collected at the lower voltage.

B.- ~ stay approximately the same because the detector is operating at saturated conditions.

C.

increase because fewer primary ions are recombining in the

-detector prior to reaching the electrodes.

D.

increase because more secondary ionizations are occurring in the detector.

ANSWER:

D.

QUESTION:

15 TOPIC:

291003 KNOWLEDGE:

K1.03 OID:

B1317-(Rev)

Which one of.ne following controller types-is designed to control-the measured parameter at-the controller set point?

A.

Integral B.

Proportional C.

On-Off D.

Derivative ANSWER:

A. u

r USgtRC GEIEERIC FUNDAMEBITALS EXAMINATIOlt OCTOBER 1997 BWR - FORM A QUESTION:

16e TOPIC '

291003 luf0WLEDGE:

Kl.05-

-QID:

B1416 (Rev)-

Which one of'the following describes a characteristic of pneumatic'

' valve _positioners?

A.-

They can_ provide auto and manual demand signals to valve controllers and valve actuators.

4 B.

-They can automatically increase or decrease air pressure to valve' actuators to overcome sluggish valve response.

l C.-

They_can either receive or supply air to/from valve controllers, depending on the direction of valve travel.

D.

They can increase air pressure to valve actuators above existing main air header pressure.

ANSWER:

B.

_ QUESTION:

17 TOPIC:

291003 KNOWLEDGE:

Kl.06 OID:

B1815 A-diesel generator is supplying a bus with the governor operating

+

in the isochronous mode.

If a large electrical load is started on the generator bus, generator frequency will:

A.

remain constant during and after load start.

B.

initially decrease'and then increase and stabilize below the initial value.

C.-

initially decrease and then-increase and stabilize at the initial value.

D.- -initially decrease and then increase and' stabilize above the initial value.

ANSWER: C.

- 13=-

T US30tC GENERIC FUNDAMENTALS EXANINATIONf OCTOBER 1997 BWR :- FORM A -

QUESTION:

18 TOPIC:

'291004 KNOWLEDGE:

K1'.01 QID:

B1718 Starting a centrifugal pump with the discharge valve throttled (versus fully open)

_ the possibility of pump--runout and the possibility of pump cavitation.

A.

increases; decreases B.

increases; increases C.

decreases: decreases D..

decreases; increases ANSWER:

C.

QUESTION:

19.

TOPIC:

291004 KNOWLEDGE:

Kl.07 QID:

B419 (Rev)

A centrifugal pump is circulating water at 150*F in a cooling water system.

After several hours the water temperature has decreased to 100*F. -Assuming system flow rate (gpm) is constant, pump motor amps will have because has increased.

A.

increased; water density B.

increased; motor efficiency C.

decreased; water density D.

decreased; motor efficiency ANSWER: A.,

w,

e

C USNRC GENERIC FUNDMIENTALS EXANINATION OCTOBER 1997 BWR FORN A-QUESTION:- 20 TOPIC.

.291004

-KNOWLEDGE:

Kl.06 QID:-

B1918 Refer to the drawing of a cooling water-systen (see-figure-below).

-The available net positive suction head for the centrifugal pump will--be decreased by:

A.-

opening surge tank makeup valve "A"

to raise tank level.

B.-

throttling heat exchanger cooling water valve "B" more cpen.

C.

throttling pump discharge valve "C" more open.

. D ~. - reducing the heat loads on the cooling water system.

ANSWER:

C.

A COOUNG A

WATER SURGE MAKEUP h

TANK ex5EdoER m

)"

[3 L Uo*00s C

o*

PUMP COOLING WATER SYSTEM

~. -

USNRC.CENERIC FUNDAMENTALS EXAMINATION OCTOBER:-1997 BWR - FORN A-LQUESTION:

'21 TOPIC:

291004 KNOWLEDGE:

Kl.13/Kl.19.

QID '

B1724 4

Two identical: centrifugal pumps (cps) and two identical positive displacement pumps-'(PDPs)-are~able.to take suction on a vented'

water storage: tank and provide makeup water flow to a cooling water system.. The pumps are capable of being cross-connected to provide

-multiple configurations.

In single pump alignment, each pump will

(

supply 100 gpm at a system pressure of 1000 psig.

Given-the~following information:

Centrifugal Pumps Shutoff head:

1500 psig Maximum design pressa.e:

2000 psig Positive Displacement Pumps _

Maximwn design pressure:

2000 psig Which one of the following pump configurations will supply the lowest makeup flow rate to the system if system pressure is at 1700 psig?

A.

Two CPn in parallel B.

Two: cps in serics C.

One PDP and one CP in parallel D.

One PDP and one CP in series (CP supplying PDP)

ANSWER: A.

s

. ~....-.

m.

k.'

' ~

USNRC Grit 2IC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A e

. QUESTION:

22 TOPIC:

291004 KNOWLEDGE:

Kl'.11 QID:

B925-

-Refer to-the drawing of a centrifugal pump operating curve l(see figure-below).

Which one of'the following determines the general' shape-of the curve from point D to point.B?

A.

Pump flow losses due to the decrease in available net positive '

suction head as the system flow rate increases B.

Pump flow losses due to back leakage through the clearances between thc3 pump impeller and casing as the D/P across the pump increases C.

Tho' frictional and throttling losses in the piping system as the system flow rate increases D.

The frictional losses between the pump impeller and its casing as the differential pressure (D/P) across the pump increases ANSWER:

C.

POINT A

/

PUMP POINT B HEAD POINT D POINT C l

FLOW l

=,

- CENTRIFUGAL PUMP OPERATING CURVE 4,

_ ~.

. - ~.. -.- ~

--~

USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR.- FORM A.

-QUESTION:

23

,. TOPIC :

291004-KNOWLEDGEi' K1.06' QID:

B1120 (Rev)

-7. motor-driven centrifugal pump is operating in an open system.

If the pump-discharge' valve is fully opened from a throttled position,

.available:netLpositive suction head (NPSH) will.

and 1

required.NPSH will A.

increase; increase B.

increase; remain the same C.

decrease; increase

.D.

decrease; remain the same ANSWER:

C.

QUESTION:

24 TOPIC:

291004 KNOWLEDGE:

Kl.18 QID:-

B1125 Which one of the following describes the proper location for a relief valve that will be used to prevent exceeding the design

-pressure of a positive displacement pump and associated piping?

A..

On the pump discharge piping upstream of the discharge isole. tion valve -

B.

On the pump discharge piping downstream of the discharge isolation valve C.

On the pump suction piping upstream of the suction isolation valv D.

On the pump suction piping downstream of the suction isolation va'lve ANSWER:

A.

USIOtc GENERIC FUNDMEENTALS EXAMINATION OCTOBER 1997 BNR

'FORN A QUESTION:

25 TOPIC:

291004 KNOWLEDGE:

K1.04 QID:-

B1219 (Rev)

Refer to the drawing of a pump with a recirculation line (see figure below).

Valve "A" will close when pump:

A.

discharge-press'tre reaches a high set point.

B.

discharge pressure reaches a low set point.

i C.

flow rate reaches a high set point.

LD.

flow rate reaches a low set point.

ANSWER: C.

A VALVE

.:. ORIFICE

]

DISCHARGE i

r f_

7 SUCTION PUMP PUMP WITH RECIRCULATION LINE

-_ ~

J USNRC GENERIC N MEMTALS EXAMINP. TION OCTOBER 1997.BWR - FORN A-QUESTION-26~

TOPIC:

291005 KNOWLEDGE:

Kl.01 QID:

B1026 A motor-driven centrifugal pump-exhibited-indications of pump failure while being started.

Which one of the following_ pairs of-

-indications will occur if the pump failure is a sheared impeller shaft?

A.

Excessive duration of high' starting current and motor breaker trips-B.

Excessive duration of high starting current and no change in i

systom flow rate C.

_ Lower than normal running current-and motor breaker trips-D.

Lower than normal running current and no_ change in system flow rate ANSWER:

D.

QUESTION:

27-TOPIC:

291005 KNOWLEDGE:

K1.05 QID:

NEW Two identical 4160 Vac induction motors are connectd:to identical centrifugal pumps being used to provide cooling water flow in separate systems in a_ power plant.

Each motor is rated at 1000 hp.

The discharge valve for pump A-is fully open and the discharge valve for_ pump B is fully shut.

If each motor is then started, une longest time period required to stabilize motor current will be experienced by motor

-and the higher stable motor current will be experienced by motor A.

A; A B..

A; B C.

B; A D._

B; B ANSWER:

A. _._.

y*

USNRC GENERIC FUNDAMENTALS EXAMINATION.

OCTOBER'1997 BWR - FORM A

. QUESTION:

28 TOPIC:

-291005 KNOWLEDGE:

K1.03

-~

QID:;

-NEW If the voltage supplied by an ac generator to an isolated-alectrical system is held constant *<hile real load (kW) is increated, the current supplied by the generator will increase in direct proportion to the _

of the change in real load.

(Assume power factor does not change.)

A.

square-root

-B.

amount C.

square D.

cube ANSWER:

B.

QUESTION:

29 TOPIC:

291005 KNOWLEDGE:

K1.04 QID:

B326 (Rev)

A centrifugal pump is operating at 600 rprr with the following parameters:

Motor current

= 100 amperes Pump head

= 50 psid Pump-flow rate = 880 gpm Which one of the following will'be the approximate value of pump head if pump speed is increased to 1200 rpm?

.A.

71 psid B.

100 psid C.

141 paid D.

200 psid ANSWER:

D.

n-i-

-~

e

_9_

USNRC raussemIC FUIEWEENTALS EXAMINATION OCTOBER 1997 BWR - FORM A e

PROOF:

_H /Ha =

(S /Sa)*

t t

Ha = H (S /s,):

3 +

3

-o Ha = SO + - 0.25 Ha =- 200 psid i

e t

+

4 4

4 ri B

).

'USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORN A QUESTION:

30' TOPIC -

291005

-KNOWLEDGE:

Kl.08 QID : ~.

B729-The main generator is operating on the grid with the following indications:

100.MWe 100 MVAR (VARs out) 2;800 amps If main generater excitation is increased slightly, amps will and MWe will _

A.

decrease;' increase B.

decrease; remain the same C.

increase; increase D.

increase; remain the same ANSWER:

D.

QUESTION:

31 TOPIC:-

291006 KNOWLEDGE:

Kl.03 QID:

B631 The rate of heat transfer between two liquids in a heat exchanger will be increased if the (Assume single-phase conditions and a constant specific heat capacity.)

A.-

flow rate.of the colder liquid is decreased by 10%.

B.

flow rate of-the hotter liquid is increased by 10%.

- C.

temperature of both liquids is decreased by 20*F.

D.

temperature of both liquids is increased by 20*F.

ANSWER:

B.

~u 4 --.

3.

' USNRC GENERIC FUNDAMENTALS EJCAMINATION -

= OCTOBER 1997 BWR - FORM-A

_ QUESTION:

32 TOPIC:

291006-KNOWLEDGE:

K1'.07 QIDJ B1231-

' Refer to the drawing of a water cleanup system (see figure below).

All valves-are identical and are initially 50% open.

To lower the temperature at point 4, _the operator should adjust valve in the-direction.

A.

A; open B.

B; shut C.

C; open D.-

D; shut ANSWER:

B.

RE RN FROM SYSTEM SYSTEM o

540*F i'2 1

A 450*F HEAT 8

3 X

122*F C

250*F 4 EXCH NGER CoolmG 6

WATER 110*F 122*F ai7

~

ION EXCHANGER WATER CLEANUP SYSTEM i

i 24 -

t i

7

.o USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A QUESTION:

33 TOPIC:

291006 KNOWLEDGE:

K1.08 QID:

B2132 (Rev)

Refer to the drawing of a lube oil heat excha'nger (see figure below).

The lube oil heat exchanger is in service with the following inlet temperatures:

Lube oil inlet temperature:

130*F Cooling water inlet temperature:

70*F Assuming cooling water flow rate is greater than lube oil flow rate, which one of the following sets of heat exchanger outlet temperatures is possible?

(Assume both fluids have the same c,.)

Lube Oil Cooling Water Outlet Temp

_ Outlet Temo A.

90*F 100*F B.

90*F 110*F C.

100*F 100*F D.

100*F 110*F ANSWER:

A.

WAnn LUBE OIL HEAT EXCHANGER

! )

USNRC GENERIC FtprnannearrALs EXAMINATION OCTOBER 199*/-BWR - FORN A PROOF A.

is the only option that shows a cooling water temp. increase that is smaller than the lube oil-temp. decrease.

This must-be the case since cooling water flow rate is greater than lube oil flow rate.

9 I

l I

~USNRC GENERIC FUNDAMENTALS EXANINATION 7,:-

OCTOBER 1997 BNR - FORN A a

QUESTION:

34 TOPIC:

291006

-KNOWLEDGE:

Kl.13; QID:-

B1536 Which one of the following describes the state of water at.160 psig and 366*P?

A.

Saturated liquid B.

_Subcooled liquid C.

Superheated. vapor D.

Mixture of saturated liquid and vapor ANSWER:

B.

PROOF:

Put for 366*F is - '165 psia i

Poe., is 160 psig + 15 = 175 psia Po e., > Put = subcooled 1

QUESTION:

35 TOPIC:

291006 KNOWLEDGE:

Kl.18 QID:

B334 (Rev)

A plant is operating at 100% power when air inleakage results in the buildup of noncondensible gases in the main condenser.

Which one of the following will occur as a result of this air inleakage?

A.

Decreased condensate temperatt w B.

Decreased' pressure in the main. condenser

-C.

Decreased suction pressure at the condensate pumps D.-

Decreased condenser cooling water outlet temperature ANSWSR:

.D.-

i 27 -

l

?

l USNRC GENERIC FUNDAMENTALS EXAKINATION OCTOBER 1997 BWR - FORM A 9

QUESTION:

36 TOPIC:

291006 KNOWLEDGE:

Kl.16

.QID:

B1234 Refer to the drawing of a lube oil heat exchanger (see figure below).

If scaling occurs inside the cooling water tubes, cooling water outlet temperature will and lube oil outlet temperature will (Assume oil and cooling water flow rates remain the same.)

A.

decrease; decrease B.

decrease; increase C.

increase; decrease 7.

increase; increase A11SWER:

B.

coens.a Warta LUBE Ott HEAT EXCH ANGER 28 -

~.

USNRC GENERIC FUNDMOOfTALS EXAMINATION '

OCTOBER 1997 BWR - FORM A~

QUESTION:

37 TOPIC:

291007' KNOWLEDGE:

K1.05' OID:

B3371(Rev)-

How does domineralizer_ differential pressure indicate the condition of the demineralizer-resin bed?

A.-

Low differential pressure indicates-flow blockage in the demineralizer.

B.

Low differential pressure indicates that the demineralizer resin bed is exhausted.

C.

High differential pressure indicates flow blockage in the demineralizer.

D.

.High differential pressure indicates that the demineralizer-resinLbed is exhausted.

ANSWER:

C.

QUESTION:

38 TOPIC:'

291007 KNOWLEDGE:

Kl.07 QID:

B39 (Rev)

When a mixed-bed demineraliuer resin is exhausted, the resin should be replaced or regenerated because:

A.

ions previously removed by the resin will be released into sohution.

B.

the resin will fracture and possibly escape through the retention screens.

C.

particles previously filtered out of solution will be released.

D.-

the resin will physically bond together, thereby causing a flow blockage.

ANSWER:

A.

- 29.-

USNRC-GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997.BWR --FORM A QUESTION:.

39 TOPIC:.

291007-

. KNOWLEDGE:

Kl.07 QID:

B1039

'dhe-anion resin in a mixed-bed demineralizer releases ions into solution while removing-charged ions from s olu tiot...

A.

hydroxida; negatively B.

hydroxide; positively C.

hydrogen; negatively D.

hydrogen; positively ANSWER:.

A.

QUESTION:

40 TOPIC:

291008 KNOWLEDGE:

Kl.02 QID:

B1144 (Rev)

Circuit breaker local overcurrent trip flag indicators, when actuated, indicate that:

A.

a breaker trip will occur unless current is. reduced.

B.

a breaker overcurrent condition is responsible for a breaker trip.

C.

an overcurrent condition has cleared and the breaker can be closed.

D.

the associated circuit breaker has failed to trip open during an overcurrent condition.

- ANSWER:

B. J-l T

'~

USNRC GENERIC FUNDAMENTALS =EXANINATION OCTOBER 1997-BWR - FORN A QUESTION::

41-TOPIC:,

291008

-KNOWLEDGE:

Kl.03

QID: -

B1044 Which one of the following; describes a benefit of using charged springs _(in lieu of a. closing-coil or solenoid _ operator); Lo close some large' motor breakers?

A.

Springs produce faster. breaker closing.

B.

Springs can be repaired or. replaced without removing-the-breaker from service.

C.

Springs provide stored energy to allow local cycling of-the-breaker upon loss of control power.

D.

Springs will keep the breaker contacts firmly seated after closing to minimize arcing and prevent inadvertent opening.

ANSWER:

C.

QUESTION:

42 TOPIC:

291008 KNOWLEDGE:

Kl.05 OID:

B1041 (Rev)

Thermal overload devices will provide the first motor protection in the event of a/an:

A.

locked rotor.

B.

electrical short circuit.

C.

gradual motor bearing damage.

D.

sheared shaft.

ANSWER:

C.

i.

USNRC-_ GENERIC FUNDAMENTALS EXAMINATION

<e -

OCTOBER 1997 BWR FORM A.

i.

QUESTION:

43

' TOPIC:

291008-KNOWLEDGE:

K1.08 QID:

B1143 A three-phase ac generator;is being paralleled to the grid with the following conditions:

Generator frequency: 59.5 Hz Grid frequency:

59.8 Hz Generator _ voltage:

115.1 kV Grid voltage:

114.8-kV When the-generator output breaker is closed the. generator will:

A.

-acquire real-load and reactive load.

B.-

acquire real load and become afreactive load to the grid.

C.

become a real load to the grid and acquire reactive load.

D.

become a real load and a reactive load to the grid.

ANSWER:

C.

QUESTION:

44 TOPIC:

291008 KNOWLEDGE:

K1.10 QID:

B1544 (Rev)

What is an advantage of using high voltage electrical disconnects instead of breakers to isolate main power transformers?

A.

Disconnects provide positive visual indication that the circuit is broken.

B.

Disconnects-can be operated-either locally or remotely.

C.

Disconnects.are cheaper and provide the same automatic protection as a breaker.

D.

Disconnects are capable of-passing a higher current with less heating than a breaker.

ANSWER:

A.

.- l

i USNRC GEN 2RIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR

-FORM A QUESTION-45 TOPICi 292001 KNOWLEDGE:' K1.02

_QID:-

B1445-(Rev)-

LAs-compared to a prompt neutron,_a. delayed neutron, born:from the same fission event, is more likely tos-A.-

leak out of the core.

B.

be absorbed in a B-10 nucleus.

C.

undergo resonance capture in a-Pu-240 nucleus.

D.

cause fission of a U-238 nucleus.

iANSWER:

B.

QUESTION:

46 TOPIC:

292001 KNOWLEDGE:

K1.03 QID:

B945

-Regarding a-thermal neutron, the word " thermal" indicates that the neutron:

A.

Was born greater than 10'" seconds af ter. the fission event.

~

JB. -

is a product of a thermal fission reaction.

C.- was released by the: decay of fission fragments.

D.

is at the same energy level as the surrounding atoms.

ANSWER:

D..

USMAC GENERIO FUtmhbEENTALS EXAMINATIC0f l

OCTOBER 1997 BWR - F094 A

'QUESTIONt 47 "QPIC 292002 i

KNOWLLDGE:

Kl.09 OID:

B1147 i

The following are combinations of critical conditions that exist for the same reactor operating at 204 power at different times in core life.. Which one of the following combinations indicates the I

_ largest amount of excess reactivity exists in the core?

CONTROL ROD REACTOR RECIR-f POSITION CULATION FLOW A.

25% rod density 25%

D.

25% rod density 50t

. C..

5086L rod density 25%

D.

50% rod density 50%

ANSWER: C.

- QUESTION:

48 TOPIC:

292002

.KNCNLEDGE:

Kl.14 QID:

B1748 (Rev)

Sixteen hours ago, a reactor scrammed from 100%-steady state power due to an instrument malfunction.

All systems operated normally.

Given the following absolute values of reactivities added since the scram, assign a (+) or (-) as appropriate and choose the current value of

're reactivity.

Xenon

= ( ) 2.0% AK/K Fuel temperature =-( ) 3.0% AK/K Control rods

( ) 12.0% AK/K

=

Voids

( ) 4.0% AK/K

=

A.

-5.0% AK/K B.

-7.0% AK/K C.

-9.0% AK/K:

D.

11.0%'AK/K ANSWER:

B.

PROOF:

-2

+3.0 l

34 -

I

~

.--.,.L.,

e.....

,e,-,-

,,-,m.,-r

.r

.w.,%a.-,-w...-

,,r.w_.w.4

-.. nr e - - - -

{

USIIItc GRIIERIC FURR*blEIPFALS EIABIINATICII 1

OCTOBER 1997 DWR - F0ftM A QUESTION:

49 1

TOPIC:

292003 l

KNOWLEDGE:

K1.01

)

QIDs NEW l

Two. reactors are currently shut down with a reactor startup in progress. The two reactors are identical except that reactor A has l

a source neutron strength of 100 ne'itrons per FeCond SDd reactor B f

souret, neutron strength is 200 neutrons per second. Control rods i

are stationary and Keff is 0.98 in both reactors.

Core neutron i

level has reached equilibrium in both reactors.

Which one of the following lists the core neutron levol (neutrons per second) in reactors A and B?

Reactor A Reactor B f

A.

5,000 10,000 L

.B.

10,000 20,000-i i

C.

10,000 40,000 D.

20,000 40,000 ANSWER:

A.

PROOF S/(1-K)

CR,,o a

Reactor A_

CRefo = 100/.02 5,000

=

Reactor B CR.,o = 200/.02 10,000

=

e 35 -

.-----.._,.---.----.-l

USNRC GEsEERIC FUunm M ALs EXAMINATIOtt i

OCTOBER 1997 WWR - FORM A

-QUESTION:

.50 TOPIC:

292003 KNOWLEDGE:

K1.04

.QID:

NEW Which one of the following percentages of fuel undergoing fission An a reactor will result in the largest rea. tor core effective delayed neutron fraction?

i U-235 U-238 Pu-239 A.

90%

7%

3%

t

~

B.-

80%

6%

14%

C.

.70%

7%

23%

~I D.

60%

6%

34%

ANSWER:

A, i

f

+

1 i

! l t

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

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

USNRC GENERIC FUlmhttENTALS EXAMINATION 1

OCTOBER 1997 BWR - FORM A J

QUESTION:

51 TOPIC:

292003 I

KNOWLEDGE:

K1,06 I

i OID:

81250 Two ruactors are identical in every way except that reactor A is at the end of core life and reactor B is at the beginning of core-i life.

Both reactors are critical at 10S% power.

If the same amount of positive reactivity is added to each reactor l

(4t the same time, the point of adding heat will be reached first by, l

reactor because it has a,_

delayed neutron fraction.-

l

A.

A; larger B.

B; larger

^

i C.

A; smaller D.

B; smaller ANSWER:

C.

QUESTION:

52 TOPIC:

292004 KNOWLEDGE:

Kl.02 QID:

B742 (Rev) l Under which one of the following conditions is a reactor core most i

likely to have a positive moderator temperature coefficient?

A.

Low coolant temperature at beginning-of-life B,

Low coolant temperature at end-of-life C.

High coolant temperature at beginning-of-life D.. High coolant temperature at end-of-life e

ANSWEN:

B.

i I

e I

h >

,_-.i m

USMRC camensIC FtpsnarmarrALs EXAMINATION l

OCTOBER 1997 BWR - FORM A l

QUESTION:

53 TOPIC:

292004 i

KNOWLEDGE:

Kl 04 QID:

B1553 l

k A_ reactor is operating at 70% power.

Which one of the following will directly result in a less negative fuel temperature i

coefficiert?

(Consider only the effect of the change in each i

listed parameter..)

i i

A.

Increase in Pu-240 inventory in the core B.

Increase _in moderator temperature C.

Increase in fuel temperature D.-

Increase in void fraction j

ANSWER:

C.

QUESTION:

54 TOPIC:

292005 KNOWLE9GE:

Kl.04 QID:

B755 (Rev)

A reactor is critical below the point of adding heat (POAH) during a reactor startup at the end of core life.

Control rods are withdrawn for 20 seconds to establish a positive 30-second reactor period.

Reactor power will increase:

A.

continuously until control rods are reinserted.

B.

and stabilize at a value slightly below the POAH.

C.

temporarily, then stabilize at the original value.-

D.

and stabilize at a value equal to the POAH.

a

. ANSWER:

D.

- 38'-

.~.

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

USNRC naaramIC FUNDAMENTAM EXAMINATIO0f OCTOBER 1997 SWR - FORM A I

QUESTION:

55

{

TOPIC:

292005 KNOWLEDGE:

Kl.07 QID '

NEW Which one of the following parameters typice.ll/ has the greatest i

influence on the chape of a differential red worth curve?

A.

Core radial neutron flux distribution B.'

Core axial neutron flux distribution C.

Core xenon distribution D.

Burnable poison distribution l

ANSWER:

B.

QUESTION:

56 TOPIC:

292005 KNOWLEDGE:

Kl.09 QID:

B357 If'the void fraction surrounding centrally located fuel bundles increases, the worth of the associated control rod (s) will:

A.

decrease, because.more neutrons are able to travel from one fuel bundlo to the next without being absorbed by the control rod.

B.

increase, because thermal neutrons will travel farther.

resulting in a larger fraction of thermal neutrons being i

absorbed by the control rod.

4 C.

decrease, because more neutrons are resonantly absorbed in the fuel as they are being thermalized resulting in fewer thermal neutrons to be absorbed by the control rod.

D.

increase, because control rod 9 are epithermal neutron absorbers and neutrons' remain at higher' energies longer due to the longer 4

slowing down length.

ANSWER: C. ;

_ _ - _ _ -. _ _ _ _ _ _.. _ _ _ _. _. - ~ _ - _......__-.

USNRC ammlIC FUNDMIENTALS EXANIMATION l

OCTOBER 1997 BWR - FORN A

?

QUESTION:

57

'M)PIC :

292005 KNOWLEDGE:

Kl.12 -

QID:

B656 During reactor power operations, the axial neutron flux shape is f

affected most by withdrawal of control rods and the r

radial neutron-flux shape is affected most by withdrawal of control rods.

1 A '.

shallow; shallow I

B.

deep; shallow

. 1 C.

shallows deep 1

D.

deept. deep i

ANSWER:

C I

l QUESTION:

58 TOPIC:

292006 KNOWLEDGE:

Kl.G2 QID:

BS5 Which one of the following lists the proper order of substances

- from.the largest to the smallest microscopic cross sections for absorption of thermal neutrons?

A.

Gadolinium, U-235, Xe-135, U-238 D.

Gadolinium, Xe-135, U-235, U-238 C.

Xe-135, U-235, gadolinium, U-238 D.

Xe-135, gadolinium, U-235, U-238 ANSWER: D.

e v

40 -

.--,-.en-e-

e

,e w

.ewn a.%

w -

--e A -

,,n v -,

w--v--*---,--

-w v~

~n--

---e---

~. ~. - - -

f USMRC GENERIC FUNDhMENTALS EXAMINATION l

OCTOBER 1997 DWR - FORM A s

QUESTION:

59 j

TOPIC:

292006 l

KNOWLEDGE:

Kl.04 i

QIDt.

.B1759 (Rev)

[

t Which one of the following describes the change in core xenon-135 concentration immediately following a power increase from 50%

i equilibrium conditions?

l A.

Initially decreases due to the increased rate of xenon-135 f

radioactive decay.

i "B.

Initially decreases due to the increased absorption of thermal neutrons by xenon-135.

C.

Initially increases due to the increased xenon-135 production 3

from fission.

D.

Initially increases due to the increased iodine-135 production from fission.

ANSWER:

B.

f L

t QUESTION:

60 TOPIC:

292006 KNOWLEDGE:

K1.07 QID:

B1561 Which one of the following reactor startup conditions requires the least amount of control rod withdrawal to attain reactor criticality during peak core xenon-135 conditions after a reactor scram from equilibrium core xenon-135 conditions?

I A.

Scram from 20% power at beginning of core life (BOL)

B.

Scram from 20% power at end of ccre life (EOL) f C.

Scram from 100% power at BOL D.

Scram from 100% power at EOL ANSWER:

A.

/

i

/=

l

),

...L--....,.--.-.-.-...-.-

=i

. = -....-.. - -. -.

a USSIRC GENERIC FUBIDADEEbrfALS EXANIMATION GC10SER 1997 EWR - FORM A t

a QUESTION:

61 TOPIC:

292006 KNOWLEDGE:

Kl.10 l

QID:

B1461 A reactor has been operating at 100% power for two months when a reactor scram occurs.

Four hours later, the reactor is critical and stable at 10% power.

Which one of the fc11owing operator actions is required to maintain reactor power at 10% over the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ?

A.

Add positive reactivity during the entire period B.

Add negative reactivity during the entire period C.

Add positive reactivity, then negative reactivity D.

Add negative reactivity, then positive reactivity ANSWER:

C.

i QUESTION:

62 TOPIC:

292006 KNOWLEDGEt Kl.12 QID:

B2159 (Rev)

Twenty-foor hours after a reactor scram from a long-term, steady-state, 100% power run, the core xenon-135 concentration will be

.approximately:

A.

the same as at the time of the scram and decreasing.

D.

the same as at the time of the scram and increasing.

C.

50% lower than at the time of the scram and decreasing.

D.

50% higher than at the time of the scram and increasing.

ANSWER:

A.

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

r

-,,,,~

,o

,--r-

USNRC GENERIC FUNDAMENTALS EXAMINATIOlt OCTOBER 1997 BWR - FORM A l

QUESTION:

63 TOPIC:

292006 i

KNOWLEDGE:

Kl.14 QID:

B62 (Rev)

A reactor is operatitig.at 80% power following a power reduction i

from 100% over a one-hour period.

To keep reactor power at 80%

over the next three hours, the operator must control rods or recirculation ^ flow rato.

A.

Insert; increase 4

B.

insert;4 'ecrease C.

withdrawr increase D.

Withdraw; decrease ANSWER:-

C.

QUESTION:

64 TOPIC:

292008 KNOWLEDGE:

Kl.03 QID:

Bl?66 t

A reactor startup is in progress with a current K.cc of 0.95 and a current equilibrium source range count rate of 150 cps.

Which one of the following equilibrium count rates will occur when Kerr becomes 0.987 A.

210 cpn B.

245 cps C.

3 f)0 ' cps D.

375 cps ANSWER:

D.

PROOF:

CR /CR

=, (1 - K ) / (1 - Ka) 3 t

3 CR

(.05/.02) 150

=

3

= 375 1

USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORN A QUESTION:

65 i

TOPIC:

292007 KNOWLEDGE:

K1.03 OID:

81163 Refer to the drawing of K.,, versus core age (see figure below).

The decrease in K.,, from point 1 to point. 2 is primarily caused by:

A.

depletion of fuel.

B.

burnout of burnable poisons.

C.

initial heat up of the reactor.

D.

buildup of fission product poisons.

' ANSWER:

D.

3 K,g i

2 4

Core' Age K,g VERSUS CORE AGE B a w.,n--

y

,, +,,

n

,J.A.=5a m

., sus 4 4 - JLp m 4-h 4 e4.---Je.a-.M 4 a u.se.4

-_g6a.g4,mA+ 4,_.

g am 4h4_4.e 4 4.wah Amm 4. J.444h, A. maa mM5 M 4Ad w.i-. a e se A-adha 4 3a34m esh. za %eM.6da

. hs m.nem x As4J-.J.5A,mw..

.a4J 6

4

{

L L

t 0 0

f USMRC GEIEERIC FUlmh3EElfTALS EXAttIBRATIOtf I

OCTOBER 1997 BWR - FORBI A l

3

' f r

i f

I t

v I

I i

L P

l.

I r

It

[

t

?

1

' h

{

h I

I F

+

t I

l, f

I 4

s b

8 i

I s _

T.

t t

k 6

5 4:

i f

M T

t k.

1

I USMRC GENERIC FUNDMEENTALS RIANIMATION OCTOBER 1997 BNR - FORM A QUESTION:

66 i

. TOPIC:

292008 KNOWLEDGE:

Kl.04 I

QID:

B67 (Rev) 3 As a reactor approaches criticality during a reactor startup it takes longer to reach an equilibrium neutron count rate after each j

control rod withdrawal due to the increased:

l A.

length of time required to complete a neutron. generation.

B.

number of neutron generations required.to reach a stable neutron level.

C.

length of time from neutron birth.to absorption.

D.

. fraction of delayed neutrons being produced as criticality is approached.

ANSWER:

B.

i

. QUESTION:

67 i

TOPIC:

292008 I

KNOWLEDGE:

Kl.08 QID:

B1069 A reactor is critical just below the point of adding heat (POAH) at a temperature of 160*F.

Which one of the following will result in reactor power increasing and stabilizing at the POAH?

(Assume a negative moderator temperature coefficient.)

A.

Reactor recirculation flow increases 10%.

-B.

Reactor coolant temperature increases 3*F.

C.

'A single control rod moves in one notch.

D.

Core xenon-135 concentration decreases.

ANSWER:

D.

, i

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

?

USamC GENERIC FUNDhMENTALS EXAMIHkTION

[

0 OCTOBER 1997 BNR - FORM A f

QUESTION:

68 TOPIC:

292008

. KNOWLEDGE:

Kl.12

-l QID:

B133 (Rev) l I

A reactor startup is in progress and criticality has just been i

achieved.

After recording critical rod height, the operator l

withdraws control rods for 20 seconds to eatablish a positive 30-1 second reactor period.

One minute later (prior to the point of l

adding heat) the operator inserts the same control rods for-25 l

seconds.

l During the insertion, the reactor period will become:

i A.

infinity during the entire period of control rod insertion, B.

negative after the control rods pass tnrough the critical rod height.

C.

negative just as the control rods pass through the critical rod' height.

D.

-negative before the control rods pass through the critical rod height.

ANSWER:

D.

[

QUESTION:

69 TOPIC:

292008 KNOWLEDGE:

Kl.15 QID:

B469 A reactor is stable at the point of adding heat (POAH) with the reactor coolant at 160*F during the reactor heat-up aad pressurization phase of a reactor startup.

Control rods are withdrawn a few notches to raise reactor power and establish a heat-up rate.

If no further control rod withdrawal occurs, reactor. power will:

(Assume no voiding oce;rs.)

A.

remain stable until voiding begins to occur.

B.

Increase until the control rods are reinserted.

C.

decrease and stabilize at a suberitical' power level.

D.-

decrease and stabilize at the POAH.-

-ANSWER:

D.

l

- r

O

[

e USNRC GENERIC M ulmTALS EXAMINATION I

o OCTOBER 1997 aBWR - FORM A l

QUESTION:

70 TOPIC:

292008 KNOWLEDGE:

Kl.18 l

QID:

B1371 (Rev) l I

With a reactor on a constant period, which one of the following i

power changes requires the shortest time to occur?

A.

1% power to 4% powe:c B.

5% power to 15% power i

C.

20% power to 35% power D.,

40% power to 60% power i

ANSWER:

D.

i QUESTION:

71-l TOPIC:

292008 KNOWLEDGE:

Kl.22 QID:

B971 J

A plant is operating at 85% power when a failure of the steam pressure control system opens the turbine control valves to admit 10% more steam flow to the main turbine.

No operator actions occur and no protective system actuations occur.

How will reactor power respond?

(Assume the valves remain in the failed position.)

A.

Increase until reactor power matches the new steam demand B.

Increase continuously and exceed reactor protection set points C.

Decrease and stabilize at a lower power level and steaming rate D.

Decrease and stabilize at a critical power level below the point of adding heat ANSWER:'

C.

I 2

~..-

_, ~,, -, -.

USNRC GEIBERIC FUNDhMENTALs EXAMINATIOtt OCTOBER 1997 BWR - FORN A QUESTION:

72 TOPIC:

292008 KNOWLEDGE:

K1.30 QID:

B131 (Rev)

)

A reactor has been operating at 100% power for several weeka when a l

reactor scram occurs.

How much time will be required for core heat production to decrease to 1% following the scram?

-A.

1 to 8 days l

-D.

1 to'8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months l

C.

1 to 8 minutes 1

D.

1 to 8 seconds l

-ANSWER:

B.

i

?

e i

E v

'I l

e

\\

i 4

i

- 49'-

.. - 2

t USMRC GENERIC FUIRahadENTALs EXAMINATIOtt-OCTOBER 1997 BWR - FORM A j

QUESTION:

73 TOPIC:

293001 KNOWLEDGE:

Kl.03 QID:

B1174 t

1 Refer to the drawing of four identical tank differential pressure

. level detectors (see figure below).

The tanks are identical and are presently at 2 psig overpressure and the same constant water level and a temperature of 60*F.

They are surrounded by atmospheric pressure.

All level detectors have been calibrated and are producing the same Icvel indication.

A leak-in the top of each tank causes a complete loss of overpressure in both tankd.

. Which level detector (s) will produce the lowest level indication?

A.

1 B.

2 C.

1 and 4 D.

2 and 3 ANSWER:

D.

M*::::J::

(

l Af

M.

. Ad/>

..y;.

..g;..

M T :J::

M

AMJ:i'"

.m.

Q-

=y;.-

..y..

TAsek DeFrentwitAL M_tsouRE tevrL DETEctons

. L

- ~. -.

i USNRC GENERIC FUNDMEENTALS EXAMINATION

{

OCTOBER 1997 DNR - FORM A l

QUESTION:

74 TOPIC:

293003 t

KNOWLEDGE:

K1.09 QID:

B1574

-ccneider a steam-water mixture with a current quality of 79%.

If I

pressure remains constant and heat is added to the mixture, the temperature of the mixture will and the quality of the l

mixture will (Assume the mixture remains saturated.)

l A.

remain the same; increase

-B.

remain the sames remain the same C.

increase; increase D.

increase; romain the same

[

ANSWER:

A.

t QUESTION:

75 TOi+1C:

293003 KNOWLEDGE:

K1.23 QID:

NEW.

-1.0 x 10' lbm/hr saturated steam at 30% steam quality is leaving a main turbine and entering a condenser at 2.0 psia.

Condensate is entering the hotwell at 118 degrees F.

Which one of the following is the approximate condenser heat transfer rate?

A.

3.1 x 10' Btu /hr B.

5. 8 - x 10' Btu /hr f-C.

7.2 x 10' Btu /hr D.

9.9 x 10" Btu /hr i

ANSWER:

A.

PROOF:

From steam tables:

Exhaust steam enthalpy is 1116.1 -

(0.7)(1022.2) = 400.56 Btu /,1bm-From steam tables - Condensate enthalpy is 86 Btu /lbm

-0 = m-dot delta-h 0 = (1,000,000 lbm/hr) (400.6 - 86 Btu /lbm)

Q = 314,600,000 Btu /hr

- 51'-

--~

I 4

US$1RC GENERIC FUtfDMtElfTALS EXAMINATIOtt OCTOBER 1997 StfR - FORN A QUESTION:

76 l

TOPIC:

293004 KNOWLEDGE:

Kl.04 QID:

B376 Refer to t.he drawing of a steam-jet air ejector (see figure below).

In the figure of an operating steam jet air ejector, s. team flovring from D to E undergoes a pressure and a velocity A.

decrease; decrease D.

decrease; increase C.

increase; increase D.

increase; decrease ANSWER:

D.

4 AB C

D E

l l

l STEAM n DISCHARGE

-"w%

y,,,,,

AtR

+

AIR & STEAM STEAM JET AIR EJECTOR

,,n

-, - ~ -. - -

USNRC GENERIC FU3tDhtEEFFALS EXAMINATIOtt OCTOBER 1997 BWR - FORM A

-QUESTION:

77

[

TOPIC:

293004 KNOWLEDGE:

K1.12 i

QID:

B1876 (Rev)

Condensate depression is the process of:

A.

removing condensate from turbine exhaust steam.

B.

spraying condens0te into turbine exhaust steam.

C.

heating turbine exhaust steam above its saturation temperature.'

D.

cooling turbine exhaust steam below-its saturation temperature.

ANSWER:

D.

a QUESTION:

78 TOPIC:

293005 KNOWLEDGE:

Kl.05 OID:

B278 Which one of the following is the most probable location for superheated steam in a boiling water reactor steam cycle that uses moisture separator reheaters?

A.

The inlet of the high pressure turbine B.

The inlet of the low pressure turbines C.

The outlet of the high pressure turbine D.

The outlet of the low pressure turbines ANSWER B. -

a.--

_~

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

USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORN A QUESTION:

79 TOPIC:

191004 KNOWLEDGE:

Kl.14 QID:

B1878 (Rev)

Refer to the drawing of four sets of centrifugal pump operating curvos (see figure below).

Each set of curves shows the results of a change in pump / system operating conditions.

Two identical constant-speed centrifugal pumps are operating in parallel in an open system when one pump trips.

Which set of operating curves depicts the "before* and "after' conditions described above?

i A.

1.

B.

2.

C.-

3.

D.

4.

ANSWER:

A.

PUMP PUMP

/

HEAD HEAD

/

FLOW Flow PUMP PUMP HEAD HEAD FLOW FLOW EE CENTRIFUGAL PUMP OPERATING CURVES

, e rwv -

+er

-w#

7

~-p

+r-e--

r+w+-

eM-e

-c--7 e'---e-

~ '

w

USIDLC GENERIC FUNDhMENTALS EXAMINATION OCTORAR 199r7 BWR - FORM A o

L QUESTION:

80 TOPIC:

293006 i

KNOWLEDGE:

Kl.19 i

QID:

B1181

- A plant is operating at full power when a 200 gpm reactor coolant leak occurs, which results in a reactor scram and initiation of emergency coolant injection.

Reactor vescel pressure stabilises at 900 psia and all injection pumps are operating with all pump miniflow paths isolated.

The shutoff heads for the pumps are as follows:

High pressure coolant injection (HPCI) pumps: 1200 psia

-Low pressure coolant injection (LPCI) pumps:

200 psia l

-Which pumps must be stopped quickly and why?

^ i

-A.

HPCI pumps to avoid pump overheating caused by high flow B.

HPCI pumps to avoid motor overheating caused by high flow C.

LPCI-pumps to avoid pump overheating caused by low flow

?.

LPCI pumps to avoid motor overheating caused by low ficw ANSWER: C.

f 55 -

6

+-n.v,v-,wv.,rw,g w

.o

-w

.m q

e

, -~--

-,,-r--

m

+ -

n

,n g

r USNRC GENERIC FUNDAMENTALS EXAMINATIOtt t

OC'lOBER 1997 BNR - FORN A QUESTION:

81 TOPIC:

293006 KNOWLEDGE:

K1.29 QID -

NEW Water at 90 degrees F and 50 psig is flowing through a 10-inch I

diameter pipe at 100 lbm/sec.

The pipe then splits into two pipes, a 4-inch diameter pipe and an 8-inch diameter pipe.

Disregarding any flow restrictions other than pipe size, which one of the following lists the approximate flow rates through the 4-inch and

[

8-inch diamoter pipes?

l 4-inch Pipe 8-inch Pipe f

(1bm/sec)

(Ibm /sec)

A.

20 80

'D.

25 75 C.

30 70 D.

33 67 ANSWER:

A.

i PROOF -

m = pAv ml + m2 = 100 PAlv + pA2v = 100 pv(Al +A2) = 100 pv(80) = 100 pv.= 100/80 ml = pvAl ml = 100/80 (16) ml = 1600/80 = 20 lbm/see m2 = pvA2 m2 =-100/80 (64) ml = 6400/80 = 80_.lbm/sec j

i k

55 -

y-g,,

-e

,py

.4ru.

w.-

y4-.-....v,cgipqy

>%-g-y,-9-.g

,,w r-

,---y7 igw--

Lm--

,eg-.-

Jsyr-ep-

vem--

-we,e-n

l USNRC GE(ERIC FUNDM8ENTAT,8 EXAMINATION OCYOBER 1997 BNR - FORM A QUESTION:-

82 M PIC:

233007 vNOWLEDGE:

Kl.01 QID:

NEW Which one of the following deceribes a heat transfer process in I

which convection is tSe most significant heat trans:!er mechanism?

u A.

From the reactor fuel to the core barrel during core uncovery B.

Through the tube walls in a main condenser during normal operation at 100% power C.

From the reactor fJe1 to the steam outlet of the reactor vessel during a station blackout D.

From fuel pellet centerline to fuel clad durirg normal operation at 100%-power i

e ANSWER:

C.

QUESTION:

83 TOPIC:

293007 KNOWLEDGE:

Kl.02 QID:

B1682 The buildup of fission gases in a fuel rod causes thermal conductivity of the fuel pellets to and thermal conductivity of the fill gas to (Consider only the direct effect of the fission gases.)

A.

decrease; decrease B.

decrease; increase C.

increase; decrease D.

increase; increase ANSWER:

A.

57 -

-e

+

+y--,

,g-g

,---v1---1p,

.-.w

>y-4yag-----e gv1y--y, yy, y-w--3rw, s+a-V T yr to-t'y-----

g-*-+-m+y 9'

or i

~s

i USNRC GENERIC FUNDhbEENTALS REAMINATIOtt OCTOBER 1997 BWR - FORM A i

QUESTION:

84 t

TOPIC:

293007 KNOWLEDGE:

Kl.13 i

OID:

B2183 (Rev) t The power range nuclear instruments havo been adjusted to 100%

based on a calculated heat balance.

Which one of the following r

will result in indicated reactor power being lower than actual reactor power?

A.

The feedwater temperature used in the heat balance calculation we.s 20*F higher than actual feedwater temperature.

B.

The reactor recirculation pump heat input term used in the heat balance was ITA lower than actual.

C.

The steam and feedwater flow rates used in the heat balance calculation were 10% higher than actual flow rates, e

D.

The operator miscalculated the enthalpy of the steam exiting the reactor vessei to be 10 atu/1tm higher than actual.

ANSWER:

A.

QUESTION:

85 DELETED.

1 57 -

,avn v--,, - -, -

y

--g,-r-,-nr

--,..w-

+

v.r,~.-

a..

n

,- -. ~ ~

w--

USNRC GENERIC FTAWEMEIFFALS EXAMINATION OCTOBER 1997 PWR += FORM A

+-

QUESTION:

86 TOPIC:

293008 itNOWLEDGE:

Kl.01 QID:

Bil83 i

Refer to the drawing of a pool boiling curve (see figure below).

In which region (s) of the curve does the reactor normalty operate to transfer _ hest from the fuel cladding to the coolant at 100%

power?

A.

Region I only L

B.

Regions I and II C.

Region II only D.

Regions II and III ANSWER: D.

I il 111 IV

'oo HEAT FLUX log af POOL BOILING CURVE

i USMRC GENERIC W hfefTALS EXAttINATION OCTOBER 1997 BNR - FORM A QUESTION:

87 i

TOPIC:

293008 KNOWLEDGE:

Kl.08 QID:

B287 (Rev)

{

The maximum convective heat transfer coefficient exists just prior to the beginning oft i

A.

bulk boiling.

B.

departure from nucleate boiling.

C.

subcooled nucleate boiling.

D.

saturated nucleate boiling.

ANSWER: B.

QUESTION:

88 TOPIC:

293008 KNOWLEDGE:

Kl.09 QID:

B987 (Rev)

Which one of the following describes the conditions in a fuel channel that is experiencing transition boiling?

A.

Complete steam blanketing of the fuel rod surface B.

Alternate wetting and drying of the fuel rod surface C.

Steam bubbles form and collapse on the fuel rod surface D.

Steam bubbles form on the fuel rod surface and are swept away by subcooled bulk coolant i

-ANSWER:

B.

i:

l'

, i

~. - - -

--_._._._.___..___.._-___._____..m USNRC GENERIC FUNDMEENTALS EXAMINATIOM OCTOBER 1997 BWR - FORN A QUESTION:

89 i

TOPIC:

293008 KNOWLEDGE:

K1.17 OID:

B1588 I

A reactor is operat ng at steady state 90% power.

Which one of the i

following will cause the two-phase coolant flowing upward in a fuel channel to become closer to the onset of transition boiling?

(Assume reactor power does not change unless stated.)

A.

~ Reactor pressure increases.

B.

Recirculation flow increases.

C.

Feedwater temperature decreases.

~D.

Associated bundle power decreases.

ANSWER:-

A.

J

?

4 i

QUESTION:

90 TOPIC -

293008 KNOWLEDGE:

K1.21 QID:

B1689 Given the following conditions:

10 lbm mixture of vapor and liquid Steam quality = 30%.

Prescure

= 1,000 psia Which one of the following approximates the void fraction?

A.-

10.1%

B.

11.3%

C.-

88.7%-

L D.

89.9%

ANSWER:

-D.

l PROOF:

Veit! Fraction =

Volume Steam l

61 -

. ~ - -. - - -

. - _...~

USNRC GENERIC FtpamarmsTAI,8 EXAMINATION i

-OCTOBER 1997 BWR FORM A

' Volume Steam + Volume Water l

.3(.44596)

=

.3(.44596) +. 7(.02159)

=

.133788

.133788 +.015113

=. 133788

.146901 t

.8985 = 89.9%

=

1 k

d,

-w e

e e

~ ~

(

USNRC GLitERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A

QUESTION:

91 TOPIC:-

293008

. KNOWLEDGE:

Kl.30

-QID:--

B1790 Two reactors, A and B, are operating at rated power with neutron flux radially peaked in_the_ center _of each core.

Reactors-A and B Lare-identical-except-that-reactor:A has core orificing and reactor B does not.

Both reactors have the same control rod pattern and density.

Compared to the center fuel bundle'in reactor A, the center fuel bundle in reactor B will have the critical power and_the coolant flow rate.

A.-

' lowest; lowest B.

lowest; highest C.

' highest; lowest D.

highest; highest ANSWER:-

A.

QUESTION:

92' TOPIC:

293009 KNOWLEDGE:

Kl.ll QID:

B1793 (Rev)

)

Which one of the following describes the basis for the 2200*F maximum fuel clad temperature limit?

A.

2200*F is approximately 500*F below the fuel clad melting temperature.

B.

The rate of the zircaloy-steam reaction becomes significant at temperatures above 2200*F.

C.

If fuel clad-temperature reaches 2200*F, the onset of transition boiling is imminent.

]

D.

The differential expansion between the fuel pellets and the 4

fuel clad becomes excessive above.2200*F.

ANSWER:

B.

)

s t -

l

+-

' USNRC GENERIC FUun u n yAL3 EXANIMATIOtt

=e OCTOBER 1997 BWR - FORM A

-QUESTION:-

19 3 TOPICS.

293009 XNOWLEDGE - Kl.07

QID

-B295 Operating a reactor below the linear' heat generation rate thermal li:ait preventst A.

cracking of the fuel cladding due to high stress from fuel

-pellet expansion.

B.

melting of the fuel cladding due to cladding temperature exceeding 2200*F during an anticipated transient without a scram..

C.-

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

D.

melting of the fuel cladding due to a lack of cooling following a-loss of coolant accident.

ANSWER:

A.

-QU,4STION:

94 TOPIC:

293009 KNOWLEDGE:

Kl.01 QID:

B1092 In a reactor operating at full power, the fuel bundle with the highest-power always has the:

-A.

. greatest critical power ratio.

B.

greatest radial peaking-factor, C.

smallest linear heat generation rate.

D.. smallest maximum average planar linear heat generation rate.

ANSWER:-

.B. -

n

.*wu e-9-4 er m

m e

~USNRC GENERIC FUNDAMENTALS EXAMINATION OCTOBER 1997 BNR - FORM A QUESTION:

95 TOPIC:

293009

-KNOWLEDGE:

Kl.16 QID:

B495 Refer to the drawing of a fuel rod and coolant flow channel at the beginning of core life (see figure below).

Given the following initial core parameters:

Reactor power

=

100%

Tc.or. t 500*F.

=

Tru.t c.nt run.

2500*F

=

What would the fuel centerline temperature be if, over core life, the total fuel-to-coolant thermal conductivity were doubled?-

(Acsume reactor power is constant.)

.A.

12 50 *F B.

1300*F C.

1400*F D.

1500*F ANSWER.

D.

F%

CLAD

%J FUEL PELLET

+

%J r%

%s ND Y

COOLANT COOLANT FLOW FLOW y

ll FUEL ROD AND COOLANT FLOW CHANNEL USNRC GENERIC FUNDEMENTALS EXAMINATION'-

OCTOBER 1997 BWR - FORN=A-c,

d '

PROOF AT

-Ta.

= Teoog..

v AT/2 = - (2500! -- 500) /2 -

2000/2 t-

=

1000-

=

~

t.'Tu = 500 + 1000' 1500*F'

=

a :,

b J

L i

I t

O.

- 6 (3 -

s !..

t a

s

USNRC GENERIC FUNDMEENTALS EXAMINATION 9

OCTOBER 1997 BWR - FORM A QUESTION:-

96 TOPIC:

293009 KNOWLEDGE:

Kl.26 QID:

B1396

-How is critical power affected when the axial power distribution in a-fuelibundle shifts from bottom-peaked to top-peaked?

A.

Critical power increases to a new, higher value.

B.

Critical power increases temporarily, then returns to its s

initial value.

C.

Critical power decreases to a new, lower value.

D.

Critical power decreases temporarily, then returns to its initial value.

ANSWER:

C.

QUESTION:

97 TOPIC:

293009 KNOWLEDGE:

K1.30 QID:

B2193 (Rev)

A step increase in reactor power results in a fuel rod surface temperature increase from 570*F to 590*F at steady state.

conditions.

The fuel thermal time constant is 6 seconds.

Which one of the-following is the approximate fuel rod surface temperature 6 seconds after the power change?

-A'.

574*F B,

577'F C.

580*F D.

583*F

-ANSWER: D.

PROOF:

Te = Tt + 0. 632 (Te - T )

Te = 57 0 + 12. 6 4 -

i Tc = 570 +' 0.632 (590 - 570)

T, = 5 8 2. 6 4 l-.

_ _. =

l e

l l

w :.....

USMRC OENERIC FUNDMENTALS EXAMINATION OCTOBER 1997 BWR - FORM A

. QUESTION:

98 TOPIC:

293009-KNOWLEDGEs-Kl.43 QID:

B1298 (Rev)

If reactor-feedwater temperature suddenly increases by 10*F during operation at 75% power, critical power will and bundle I

power will-(Assume the reactor does not scram.)

R

A.

increase; increase B.

increase; decrease C.

decrease; increase D.

decrease; decrease ANSWER:-

D.

I l

l QUESTION:

99 TOPIC:

293010 KNOWLEDGE:

K1.02 QID:

B1500 (Rov)

The nil-ductility transition temperature is that temperature:

1 A.

below which vessel failure is imminent.

B.

above which vessel failure is imminent.

below which the probability of brittle fracture significantly C.

increases.

4 D.

above which-the probability of brittle fracture significantly

-increases.

-ANSWER:

C.

-J /

ha

s USMRC GENERIC FUNDAMENTALS EXAMINATION 1

o OCTOBER.1997 BWR - FORM A l'

-hUESTION:

100.

TOPIC:

293010 KNOWLEDGE:' Kl.04-QID:

B899 (Rev)-

ie'

-ALheatup stress applidd to'the reactor vessel is:-

f A.-

tensile'at the inner wall and compressive at the outer wall.-

'B.

tensile-across the' entire wall.

C.

compress.ive at the inner wall and tensile at the outer wall.

D.

compressive 1across the entire wall.

ANSWER:-C.

f t

./

..s.

p 000 FINAL ANSWER KEY 000-OCTOBER 1997 NRC-GENERIC FUNDAMENTALS: EXAMINATION BOILING WATER REACTOR"--ANSWER KEY

' FORM ANS FORM ANS FORM

'ANS FORM ANS A

B A

B

~A B

A B

1 29 D

26 54 D

51 79 C

76 4

D 2

30 D

27 55 A

52 80 B

77 5

D 3'

.31

.C-28 56 B

53 81 C.

'8 6

B 4 -.

~32 C'

Ti9 57 D

54 82 D-79 7

A 1

5-33-B 30 58 D

55 83 B~

80 8

C 6

34 C

31 59 B

56 84 C

81 9-A 7

35 A

32 60 B

57 85 C

82 10 C

8 36:

D 33 61 A

58 86 D

83' 11 A

I 9

37 D

34 62 B

59 87 B

84 12 A

10 38 B-35 63 D

60 88 A

85 13 C/D 11-39 A

36 64 B

61 89 C

86 14 B

12 40

.B 37 65 C

62 90 A

.87 15 B

13 41 D

38-66 A

63 91 C

88 16 B

i 14 42 D

39 67 A

64 92 D

89 17 A

15 43 A

40 68 B

65 93 D

90 18 D-C 16 44 B-41 69 C

66 94 B

91 19 A

17 45 C

42 70 C

67 95 D

92 20 B

18

=46 C

43 71 C

68 96 D

93 21 A

19 47 A

44 72 A

69 97 D

94 22 B

20 -

4 8-C 45 73 B

70 98 D

95 23 D

21 49 A

46 74 D

71 99 C

96 24 C

22-50 C

47 75

-C 72 100 B

97 25 D

~23 51 C

48 76 B

73 1

D 98 26 D

24 52--A 49 77 A

74 2

A 99 27 C

25

53

'C 50 78-A 75 a

A 100-28 C

=

. - _,

ML20199B481

Text

SUBJECT:

Enclosure:

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