ML20207L079

Forwards Results of Pilot BWR Generic Fundamentals Exam for Region II Administered on 880921

ML20207L079
Person / Time
Issue date:	10/06/1988
From:	Perkins K Office of Nuclear Reactor Regulation
To:	Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8810170169
Download: ML20207L079 (62)

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OCT 0 61988 MEMORANDUM FCR:

Caudle A. Julian, Chief Operations Branch Division of Reactor Safety Region II FROM:

Kenneth E.

Perkins Jr., Chief Operator Licensing Branch Division of Licensee Performance and Quality Evaluation, NRR

SUBJECT:

RESULTS OF PILOT BWR GENERIC FUNDAMENTALS EXAMINATION FOR REGION II.

On September 21, 1988, NRC administered a pilot Generic Funda-mentals Examination for three (3) facilities in your region.

Operator Licensing Branch has completed grading the results of the examination.

Enclosed with this memorandum are the results of the examination for your region.

Also included are copies of the Examination (forms a and b) with answers and references, and a copy of the cover letter sent to each of the Facilities in your region.

In accordance with 10 CFR 2.790 of th.s Commission's degulations, a copy of this letter and enclosure = (1) through (4) will be placed in the Public Documents Room.

The results of individual examinees are exempt from disclosure, therefore enclosure (5) will not be place in NRC's Public Document Room.

In order to expedite the processing of operator licensing i

requests the regions are delegated authority to grant waivers for candidates requesting to substitute their pilot examination 1

scores for the fundamentals portion of their licensing examin-ation (Sections 1 or 5 of.' the current examination or sections 1 or 4 of the new examination).

The waiver shall be granted if requested.

The pilot eramination score is to be used in deter-mining the results overoll results of the licensing examination.

If an applicant for either an RO or SRO license takes the current four section examination, the pilot examination results will count for 25% of the total, and if the candidate takes the new three section examination, it will count for 25% for the overall operator examination score or 24% for the overall senior operator examination score.

A candidate must still obtain an overall

/g, minimum score of 80% on his/her licensing examination to pass.

rg/ 9 Passing grade for the fundamentals section is 70%.

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8010170169 881006

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i If you have any questions concerning this letter, please contact Paul Doyle at FTS 492-1046 or Len Wiens at FTS 492-3171.

\\

Kenneth E.

Perkins, Chief Operator Licensing Branch Division of L.4censee Performance and Quality Evoluation, NRR Enclosures 1.

Examination Form "A" with ansvers and references 2.

Examination Form "B" with answers and references 3.

Copy of Cover Letters for Region facilities 4.

Copy of Voluntary Feedback Forms concerning Pilot Examina-tions for examinees sent to the facilities 5.

Copy of Voluntary Feedback Forms concerning Pilot Examina-tions for trainers sent to the facilities 6.

Examination Results for Region facilities T

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i 007 0 6 1988 i

DISTRIBUTION (w/o Enclosure 6)

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Acc: NRC87 Rubric (s): 291002K1.02 Correct Answer: 1 Comp # 3960

Reference:

NMP-2 BWR Academics, Heat Transfer and Fluid, T. Meadows, February 1985, pp. 6-66 and 6-68.

1.

A correct statement regarding the use of an crifice to measure the volume flow rate of water in a pipe is that:

1.

the measured flow rate will bc higher than the actual flow rate if the water temperature is lower than the calibrated temperature.

mperature compensation is not required to obtain accurate flow rates because water is an ompressible fluid.

'.. the measured flow rate will be lower than the actual flow rate if the water temperature is lower than the calibrated temperature.

4.

temperature compensation is not required because the pressure drop across the orifice is a viscous effect and is not temperature-dependent.

Acc: NRC54 Rubric (s): 2910071.04 Correct Answer: 2 Comp # 4029

Reference:

General Electric BWR Academics Series Chemistry,1985, pp. 5 - 15.

2.

A correct statement regarding a condensate demineralizer is that its efliciency can be determined by:

1.

performing a chemical analysis on the outlet of the dcmineralizer to detect silicate.

2.

sampling the inlet and outlet of the demineralizer to determine the change in conductivity.

3.

sampling the inlet and outlet of the demineralizer to detect a difference in radioactivity.

4.

monitoring the change in differential pressure across the demineralizer.

i Acc: NRC406 Rubric (s): 291008K1.05 Correct Answer: 2

Reference:

Commonwealth Edison Company, Power Plant Electrical Fundamentals Book 5,1979, Section 4, p.68.

3. Hermal overload devices are used to protect circuits in nominal overload conditions. Which of the following defines a thermel overload device?

1.

A balanced circuit that compares normal current to a fixed overcurrent; exceeding the normal current trips the overcurrent relay, 2.

An in line thermal coil that, when subjected to a high current, overheats and actuates a circuit-interrupting device.

3.

A temperature monitor that senses the temperature of the operatice, equipment and trips the circuit breaker if the temperature exceeds preset limits.

4.

An induction coil that generates a secondary current proportional to the primary current, closing the trip circuit contacts.

1-9/88

I NRC Exam - Form 6470101 Acc: NRC401 Rubric (s): 291001K1.01 Correct Answer: 2

Reference:

River Bend, Licensed Operator Training Manual,1987, Main Steam, pp. 7-4.

4.

Safety valves are used in BWR nuclear main steam systems to protect the reactor and the system piping from damage due to overpressurization. Which of the following statements concerning the operation of safety valves is correct?

1.

When the activating pressure for a safety valve returns to the lifting set point, a combination of air and steam pressure above the valve disk clases the valve.

2.

As reactor pressure increases to the safety set point, the pressure overcomes spring tension on the valve operator, causing the valve to open.

3.

As the disk on a safety valve lifts, less pressure is exerted on the disk, reducing the upward force on the disk, preventing "valve slamming".

4.

A safety valve is lifted off its seat, then is forced fully open by an air operated piston.

Acc: NRC372 Rubric (s): 291002K1.07 Correct Answer: 1 i

Ref:renec: GE BWR Academic Series on Instrument and Controls (November 1984) p. 2-30, 5.

Many reactor water level instruments are designed with a condensing chamber in the reference leg.

'lte purpose of the condensing chamber is to:

1.

keep the reference leg filled by condensing steam.

2.

provide pressure compensation for the reactor pressure exerted on the variable leg.

3. prevent reference leg flashing during a rapid depressurization of the reactor vessel.

4.

alleviate the need for density compensation by keeping the reference leg temperature close to the temperature of the variable leg.

Acc: NRC99 Rubric (s): 291007K1.03 Correct Answer: 3 Comp # 3904

Reference:

NRC Systems Manual BWRs, BWR/6 Design, Vol. I, Chapter 2, pp. 2.61 and 2.8-1.

6.

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

1.

results in lower fuel temperature, which increases the nuclear fuel cycle efliciency.

2.

is controlled by complying with core thermallimits.

3.

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

4.

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

. 9/88

NRC Excm - Form 6G0101 Acc: NRC389 Rubric (s): 291003K1.03 Csrrect Answer: 2

Reference:

NNECo Training Dept Unit No.1 Lesson Plan 1337 Automatic Pressure Relief (APR) System Fig 7-2, p.12.

QUESTION ? REFERS TO THE FOLLOWING DIAGRAM:

High Drywoll Pressure Low Reactor l

Water Level i,

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1 O

Push Button I

i Roset O

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Seal-in]I me Del y j

" "Y t

n 7.

The purpose of the sealin relay is to:

).

hold the valve open even if the reset pushbutton is pressed.

2.

hold the valve open enn if the initiating conditions reset.

3.

close the valve as soon as either initiating condition resets.

4.

close the valve only when both initiating conditions reset.

Acc: NRC373 Rubric (s): 2910021.1.07 Correct Answer: 3

Reference:

GE IlWR Academic Series on Instruments and Control (November 1984) pp. 2 30, fig. 2 26.

3.

Which of the fellowing parameters determines the maximum level that can be indicated by a reactor water level instrument?

1.

The elevation of the differential pressure cellin relation to the auxiliary condensing chamber j

2.

The elevation of the reference leg condensing chamber 3.

The level at which the reference leg penetrates the reactor vessel 4.

'Ihe level at which the variable leg penetrates the reactor vessel l

-3 9/88

NRC Exam - Form 6470101 Acc: NRC83 Rubric (s): 291002K1.01 Corrsct Answer: 1 Comp # 3935

Reference:

NMP 2 BWR Academics, IIcat Transfer and Fluid Flow, T. Meadows, February 1985, pp. 667 and 6-70.

9.

A correct statement concerning a Venturi flow device is that it:

1.

develops an output signal by measuring the differential pressure of the fluid as it passes through the device.

2.

can measure the rate of flow of incompressible fluids, but not of compressible fluids.

3.

develops an output signal by measuring the velocity of the fluid as it passes through the device.

4.

has head losses greater than the head losses produced by an orince.

Acc: NRC394 Rubric (s): 291003K1.06 Cortzet Answer: 4

Reference:

NNeco Training Dept. Unit No.1, Lesson Plan,1338, Emergency Diesel Generator, p.13.

10. A correct statement regarding the function of a governor on an emergency diesel generator is that it:

1.

trips the dieret in the eunt of engine overspeed.

2.

regulates the amount of fuel supplied to the engine, to increase engine speed as load increases.

3.

maintains generator output voltage and frequency constant as the load changes.

4.

regulates the amount of fuel supplied to the engine, to produce a nearly constant engine speed as load changes.

Acc: NRC90 Rubric (s): 291004K1.04 Correct Answer: 2 Comp # 3702

Reference:

NMP 2 IlWR Academics, lleat Transfer and Fluid Flow, T. Meadows, February 1985, p. 6108.

11. Operating a motor driven centrifugal pump for extended periods of time with the discharge valve shut will result in:

1.

no damage, since the pump and motor are designed to operate with the discharge valve shut.

2.

the pump overheating, cavitation, and ultimately pump failure.

3.

excessive motor current, damage to motor windings, and ultimately motor failure.

4.

pump and motor overspeeding and tripping on high mstor current.

I e

1 9/88

NRC Ex:m - Form 6470101 Acc: NRC96 Rubric (s): 291005K1.05 Cctr:ct Answer: 3 Comp # 3655 R ftrence: NMP-2 BWR Academics, IIcat Transfer and Fluid Flow, T. Meadows, February 1985, p. 6108.

12. The average starting current for an alternating current motor that provides power for a pump is approrimately:

1.

the same as its normal running current 2.

two times its normal running cuarent 3.

five times its normal ruaning current 4.

ten times its normal running current Acc: NRC229 Rubric (s): 291006K1.18 Corrzet Answer: 1 Comp # 3912

Reference:

General Electric BWR Academics Series IIcat Transfer and Fluid Flow,1985, pp. 7 28 to 7-29.

13. Proper venting of a shell and tube heat exchanger is important because:

1.

air is a good insulator and has a poor heat transfer coefficient.

2.

the air bubble hinders the flow of cooling water.

4 3.

the air bubble will cause thermal shock as it moves through the heat exchanger.

4.

the air bubble will cause corrosion in the heat exchanger.

Acc: NRC104 Rubric (s): 291006K1.01 Correct Answer: 2 Comp # 3916 i

Reference:

NRC Systems Manual BWRs, BWR/6 Design, Vol. 2, Chapter 10, p.10.414.

14. As steam (shell) and liquid (tube) heat exchangers are put into service, the:

1.

steam side is valved in before the water side to minimize scale buildup on the heat exchanger tubes.

2, water side is valved in before the steam side to prevent thermal shock from occurring.

3. water side is valved in before the steam side to ensure adequate venting.

4.

steam side is valved in before the water side to ensure that the cooldown rate does not exceed design limits.

l j

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9/88

NRC Exam - Form 6470101 Acc: NRC414 Rubric (s): 291002K1.09 Cctreet Answer: 3 4

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Reference:

BWR Training Guide, Fluid Dynamics, Section 3,1970.

15. Reactor feedwater flow and vessel level detectors use differential pressure (D/P) cells to measure flow and level. If a level D/P cell diaphragm fails, the level indication:

1.

will go to 0.

2.

will slowly move to 50% (midrange).

3.

will indicate 100% (full range).

4.

remains the same.

Acc: NRC411 Rubric (s): 291008K1.08 Corrzet Answer: 2 l

Reference:

River Bend Station, License Operator Training Manual,1987 (LOTM-10) Main Generator, p.

29.

16. Closing a circuit breaker between two electrical generating systema that are out of phase will result in:

1.

negating the reverse power protection on te tagging frequency system.

2.

a rapid phase alignment which could damage generators and loads connected to the system.

3.

a voltage reduction in both generating systems.

4.

reduction of the frequency of the combined generating system.

Acc: NRC396 Rubric (s): 291005K1.08 Correct Answer: 1 I

Reference:

General Electric BWR Academics Series 1985, Electrical Science, AC Generators and Motors.

l

17. Generator excitation controls the megavar loading and power factor of generators operating synchronized to a grid. Which of the following characteristics will an underexcited generator exhibit?

l 1.

Negative megavars and a leading power factor l

2.

Dositive megavars and a leading power factor 3.

Positive megavars and a lagging power factor 4.

Negative megavars and a laging power factor Acc: NRC85 Rubric (s): 291002K1.15 Correct Answer: 1

]

Comp # 3938

Reference:

NRC Systems Manual BWRs, BWR/6 Design, Vol. I, Chapter 3, pp. 3.112 arid 3.113. Mark's Standard llandbook for Mechanical Engineers, Eighth Edition, p.16-13.

18. A correct statement regarding thermocouples is thet they:

1.

will indicate low offscale with an open circuit.

2.

are more accurate than resistance temperature detectors.

a I

3.

are made up of two similar metals in contact at one end, called the hot junction.

4.

are based on the inherent characteristic of metals that results in a change in electrical resistance with a change in temperature.

j 9/88

NRC Exem - Form 6470101 Rubric (s): 291004K1.12 i

Acc: NRC92 i ' Correct Answer: 3

)

Comp # 3718 RGference: NMP 2 BWR Academics, IIcat Transfer and Fluid Flow, T. Meadows, February 1985, p. 6-109.

19. Operating a motor-driven centrifugal pump under "pump runout" conditions causes:

1.

pump overheating, cavitation, and ultimately pump failure.

2.

no damage, since the pump and motor are designed to operate without failure under pump runout conditions.

3.

excessive motor current to be drawn, damage to the motor wLdings, and ultimately motor failure.

4.

excessive motor current to be drawn, overheating of pump and motor hearings, and ultimately i

pump failure.

Acc: NRC88 Rubric (s): 291004K1.06 Correct Answer: 1 Comp # 3618

Reference:

NMP-2 BWR Academics, Ileat Transfer and Fluid Flow, T. Meadows, February 1985, pp. 6-76 through 6 81.

20. Which one of the following will be most likely to increase reactor recirculation pump available net positive suction head?

1.

Loss of feedwater heating while at 80% power l

2.

Increase in reactor coolant temperature from 100'F to 200*F during a reactor startup I

3.

Decrease in reactor pressure during a normal reactor shutdown i

4.

Decrease in reactor water level from the normal level to just below the low-level alann level Acc: NRC225 Rubric (s): 291004K1.17 Correct Answer: 4 Comp # 3956 Referenue: General Electric BWR Academics Series IIcat Transfer and Fluid Flow,1985, p. 6-89.

21. Operating a positive displacement pump with insufficient net positive suction head will cause which one of the following to occur?

1.

Slip 2.

Decreased pump speed 3.

Viscosity loss 4.

Vapor binding i

7-9/88

NRC Excm - Form 6470101 l

Acc: NRC80 Rubric (s): 291001K1.12 Correct Answer: 1 Comp # 3966 l

R3ference: NMP-2 BWR Academics, Heat Transfer and Fluid Flow, T. Meadows, February 1985, p. 6 39.

22. For throttling, globe valves are preferred over gate valves because:

1.

the loss coefficient is generally more linear for globe valves than for gate valves.

2.

the loss coefficient for a full open globe valve is smaller than the loss coefficient for a full open l

gate velve.

l

3. valve position indication for a midpositioned valve is more reliable for globe valves than for gate l

valves.

l 4.

valve motor operators are more adaptable to globe valvcs than to gate valves.

Acc: NRC114 Rubric (s): 292006K1.11 2

Correct Answer: 1 Comp # 3990 i

Reference:

General Physics Corp., Academic Program for Nuclear Power Plant Perso.nel, Volume II, Physics, Chapter 5, p. 5 5 - 56.

I

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23. A power reactor has been operating at 50% power for 4 days. Power is then increased to 100% over j

a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. Which of the following expresses the time range during which the minimum l

concentration of xenon is expected to occur after the power increase?

1, 4 - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> i

2.

10 - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i

3.

15 - 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> 4.

19 - 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> Acc: NRC56 Rubric (s): 2920011.02 i

Correct Answer: 3 l

Comp # 4001

Reference:

General Electric BWR Academics Series, Rector Theory,1984, pp. 3 - 21.

0

24. Which one of the following is the best definition of the term prompt neutron?

l q

A high-energy neutron emitted from a neutron precursor,immediately after the fission process.

1.

2.

A neutron with an energy Icvel greater ti;an 0.1 MeV, emitted in less than 10-4 seconds following a nuclear fission.

3. A neutron emitted in less than 10-H seconds following a nucient fission.

4.

A neutron emitted as a result of a gamma n or alpha n reaction.

i 1

i l

i 8-9/88 L..

NRC Exam - Form 6470101 1

Acc: NRC42 Rubric (s): 2920081.19 Correct Answer: 2 Comp # 3933 RGference: Brunswick, Steam Electric P! ant, Reactor neory, ch.14, p.190.

i

29. Assume a BWR plant is at 20% power. Power is increased to 30% by control rod withdrawal. Which one of the following statements best describes the change in void fraction?

1.

Void fraction initially decreases, then linearly increases with rod worth increase.

2.

Void fraction increases.

l 3.

Void fraction decreases.

4.

Void fraction tercams the same, j

Acc: NRC182 Rubric (s): 292008K1.03 Correct Answer: 2

)

Comp # 4109 l '

Reference:

General Electric BWR Academics Series, Reactor neory 1984, pp. 7-7.

f l

36. Assume your reactor is being taken critical by periodically withdrawing equal reactivity control rod i

increments. Which of the following statements is correct as K,, approaches unity?

t 3

1. De neutron level change for successive rod increment pulls becomes smaller.

2.

A longer period of time is required to reach the equilibrium neutron level after each rod l

withdrawal.

3.

A rod withdrawal will result in the reactor becoming slightly supercritical, due to a "prompt jump", and then return to a suberiticallevel.

t 4.

If the rod withdrawal is stopped for several hours, the neutron level will decrease to source level, l

Acc: NRC59 Rubric (s): 2920021.11 i

Correct Answer: 4 l

Comp # 4025 i

i

Reference:

General Electric BWR Academics Series, Reactor neory,1984, pp.1 - 38.

4 l

27. Which one of the following terms is defined as the fractional change in neutron population from one i

generation to the next?

i l

l 1.

AK

)

2.

K,,

3.

K,,-t 4.

Reactivity l

1 4

l 1 9/88 i

NRC Exem - Form 6470101 Acc: NRC251 Rubric (s): 292003K1.01

. Correct Answer: 1 Comp # 4027 j

R:ference: General Electric BWR Academics Series Reactor neory,1984, pp. 3-5 to 312,

28. Of the following conditions, which three are necessary for suberitical multiplication to occur?

1.

Neutron source, moderator, and fissionable material 2.

K less than one, moderator, and control rods g

3. Moderator, neutron source, and K,,less than one 4.

Fissionable material, moderator, and K,, greater than one Acc: NRC261 Rubric (s): 292005K1.10 Corrzet Answer: 1 Comp # 3977 i

Reference:

General Electric BWR Academics Series Reactor %cory,1984, p. 5 21.

29. Which one of the following is the best reason for "flux shaping"?

1.

To minimize the potential of moving high worth control rods f

2. To allow thermal leakage to control thermal power by keeping periphery control rods iarther out of the core

3. To equalize wear and required maintenance 4.

To reduce thermal leakage by keeping periphery control rods farther into the ccre Acc: NRC175 RuHc(s): 292008K1.04 Correct Answer: 2 l

Comp # 4066 l

Reference:

General Electric 11WR Academics Series Rector Theory 1984, pp. 7-6

30. During reactor startup, which of the following does not affect critical rod position?

1.

Control rod worth 2.

Source range initial count rate 1

3.

Fuel temperature 4.

Core age j

i I

l]

i 1 9/88

NRC Fxam - F::rm 6470101 Acc: NRC145 Rubric (s): 292004K1.01 Correct Answer: 2

' Comp # 3594 Referznce: Brunswick Steam Electric Plant, Reactor neory, Chapter 14, p.164.

31. "The change in reactivity produced by a unit change in reactor coolant temperature" defines which of the following reactivity coefficients?

1.

Void 2.

Moderator 3.

Pov/er 4.

Doppler Acc: NRC153 Rubric (s): 292003K1 ^9 Correct Answer: 3 Comp # 3531

Reference:

Introduction to Nuclear Reactor Operations, Reac:or Kinetics, Reed Robert Burn, T 4 32. After initial criticality, a reactor is leveled off. The source range channels are repositioned so that the count rate is 100 cps. Sufficient positive reactivity is added to establish a 120-second period. Which of the following indicates the time it will take for the count rate to increase to 10,000 cps with no l

additional action?

1.

1.2 minutes 2.

4 minutes

3. 9.21 minutes 4.

15.82 minutes Acc: NRC305 Rubric (s): 292008K1.20 Correct Answer: 2 Comp # 4010

Reference:

General Electric BWR Academics Series, Reactor neory,1984, pp. 4-5 to 510.

33. A power increase is initiated by an increase in recirculation flow, causing voids to be swept away and adding positive reactivity. Which of the followhg statements best describes the response of the reactivity coeflicients?

1.

Increasing fuel temt.crature implies more heat transfer to the coolunt. Increased moderator temperature causes more void formation, and power stabilizes at a new higher level.

2.

Increasing fuel temperature implies more heat transfer to the coolant, thus increasing steam generation. He increased void fraction and fuel temperature add negative AK/K, and power stabilizes at a new higher level.

3.

Increasing fuel teraperature implies more heat transfer to the coolant, thus increas'ag steam generation. He increased steam generation raises reactor pressure and moderater temperaturc, offsetting the decreased volds, and power stabillies at a new higher level.

4.

Increased moderator and fuel temperature stabilize power at a new higher level. 9/88 1

NRC Exem - Form 6470101 Acc: NRC76 Rubric (s): 292006K1.22 Correct Answer: 2 i

' Comp # 3474

Reference:

Georgia Power Training Manual Plant, E.I. IIatch Revi, pp. 10.1.6-10, 10.1.6-11.

j

34. In regard to xenon and samarium concentrations following a scram from extended operation at high i

power, which one of the following statements is correct?

1.

Xenon concentration increases for the first.* hours, while samarium concentration decreases.

2.

Xenon and samarium concentrations increase for the first 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

3.

Xenon concentration increases, while samarium concentration remains at equilibrium.

4.

Xenon concentration decreases, while samarium concentration remains at equilibrium.

Acc: NRC254 Rubric (s): 292005Kl.04 Correct Answer: 4 l

Comp # 3613

Reference:

General Electric BWR Academbs Cerier Reactor neory,1984, p. 5 25.

35. He "reverse power effect" or "reverse reactivity effect" occasionally observed when a shallow control i

rod is withdrawn one or two notches is due to a relatively:

1.

large local power increase being offset by a moderator temperature-related power decrease.

2.

small local power decrease due to the "shadowing" effect of nearby control rods.

3.

small local power decrease due to increased local Doppler effects.

i 4.

large local power increase being offset by e void-related power decrease.

l Acc: NRC109 Rubric (s): 292002K1.08 Correct Answer: 1 Comp # 4005

Reference:

General Physics Corp., Academic Program for Nucler Power Plant Personnel, Volume II, Physics, Chapter 4, p. 4 - 54.

36. A reactor with a K, of 1.002 would be considered:

1.

supercritical 2.

critical 3.

suberitic al 4.

prompt critical 12 -

9/83

NRC Exam - Form 6470101 Acc: NRC162 Rubric (s): 293009K1.21 Correct Answer: 2 Comp # 3505

Reference:

Heat Transfer and Fluid Flow, BWR Acaderaics Series, General Electric, Chapter 9, page 9-15a

37. Which of the following limits or ccnditions is avolded by maintaining the minimum critical power ratio (MCPR) within specified values?

1.

1% plastic strain on cladding 2.

99.9% of the fuel pins in the core not experiencing transition boiling during a transient 3.

Gross cladding failure due to lack of cooling 4.

Fu-l cladding cracking due to high stress Acc: NRC169 Rubric (s): 293007K1.01 Correct Answer: 4 Comp # 3468

Reference:

Brunswick Steam Electric Plant, Heat Transfer, Chapter 8, page 8-2

38. Which of the following methods of neat transfer is defined by "the exchange of energy between bodies by electromagnetic waves through an intervening space"?

1.

Conduction 2.

Convection 3.

Electrokinetics 4.

Radiation Acc: NRC221 Rubric (s): 293003K1.23 Conect Answer: 4 Comp # 3939

Reference:

Steam Tables.

39 A recently calibrated pressure gauge sensing in the same area as a tempunuure L3trument indicates 350 psig. Assuming saturation conditions, which one of the following will tne temperature instrument show?

1.

420*F 2.

425'F

3. 430'F 4.

435'F 13 -

9/88

NRC Ex m - Ferm 6470101 Acc: NRC06 Rubric (s): 2930081.23 Cctreet Answer: 4 Comp # 3645

Reference:

Westinghouse Hermal Dynamic Principles and Applications, ch. 7, pp.13 - 14, Steam Tables 1

Mollier Diagram.

{

CD. Which of the following values most accurately represents the quality of steam leaving a cyclone separator at 985 sig and 1183 Blu/lb?

T

1. 95 %

d

2. %%

3. 97 %

4.

99 %

Acc: NRC09 Rubric (s): 2930081.07 Correct Answer: 1 3

Comp # 4015 t

Reference:

Westinghouse hermal Ilydraulic Principles and Applications, ch. O, p. 59.

41. Which of the following terms most accurately refers to the boiling that sesults when the steam bubbles moving away from a heated surface collapse in the bulk fluid?

l 1

~

l 1.

Subcooled nucleate boiliig i

2.

Saturated convection

(

4 3.

Subcooled convection T

4.

Saturated nucleate boiling l

Acc: NRC312 Rubric (s): 293008K1.34 i

Correct Answer: 1 l

j Comp # 3533 j

Referznce: General Electric BWR Academics Series, IIcat Transfer and Fluid Flow,1985, p. 8-56.

l l

42. Natural circulation is inherent in a boiling water reactor (BWR). Which one of the following j

statements best describes natural circulation after a loss of offsite power?

1.

Liquid density in the downcomer and reduction of density in the core region support the cycle.

Two phase flow in the separators allows steam to be removed and liquid to return to the 1

downcomer region, i

3.

Relief and safety valves provide a heat sink for decs,v heat. In spite of leakage, control rod drives

]

are adequate to maintain inventory.

i 4.

Density of liquid in the core region increases, thereby allowing liquid in the downcomer to enter J

the core.

l

-W-9/88

.=

NRC Exar' - Ferm 6470101 Acc: NRC148 Rubric (s): 293009K1.17 I

Correct Answer: 2 i

Comp # 3548 l

I

Reference:

Nuclear Power Plant Thermal Sciences, Reactor IIcat Generation, Reed D,obert Burn, Chapter 10, p.10 - 6.

l

43. "The fuel bundle power that would cause the onset of transition boiling at some point in the fuel bundle"is the but definition of which of the following terms?

1.

Maximum core power 2.

Critical power 3.

Maximum fraction of limiting power density 4.

Maximum power density Acc: NRC209 Rubric (s): 293007K1.13 i

4 Correct Answer: 3 r

Comp # 3510 l

Reference:

Georgia Power Nuclear Training Manual; Training Lessen Plan Cycle Efficiency and the Real j

Cycle,1985, pp.11 - 15.

)

44. In regard to conducting a reactor heat balance, which one of the following statements about determining reactor power is true?

i I

1.

If the feedwater flow rate used in the heat balance calculation was lower than the actual feedwater flow rate, then the actual power is higher than the currently calculated power.

2.

If the reactor recirculation pump heat input used in the heat balance calculation was omitted, then the actual power is higher than the cunently calculated power.

3.

If the steam flow used in the heat balance calculation was lower than the actual steam flow, then the actual power is higher than the currently calculated power.

j 4.

If the reactor water cleanup unit (RWCU) return temperature used in the heat balance calculation t

i was lower than the actual RWCU return temperature, then the actual r.ower is higher than the currently calculated power.

i Acc: NRC26 Rubric (s): 2930091.10 i

Correct Answer: 4

]

Comp # 4040

Reference:

Brunswick Steam Electric Plant, ticat Taansfer, ch. 9, p. 70, i

l

45. Which of the following thermal limits protects the fuel from reaching 2200*F following a loss-of <oolant accident (LOCA)?

I 1.

Linear heat generation rate (LilGR) 2.

Total peaking factor 3.

Maximum thermal power l

4.

Average planar linear heat generation rate (APL11GR) i 3

1 5 9/88

=

NRC Ex:m - Form 6470101 Acc: NRC49 Rubric (s): 2930051.05 Cctreet Answer: 2 Comp # 3968 Ref:rence: Brunswick, Steam Electric Piant, IIcat Transfer, ch. 6, p. 70.

46. Given a BWR steam cycle, which of the following is the most probable location for superheated steam?

1. The outlet of the h!gh pressure turbine

2. The outlet of the moisture separators /rcheaters

3. The inlet of the high pressure torbine 4.

The outlet of the low pressure turbine Acc: NRC128 Rubric (s): 293006Kl.05 j

Corr:ct Answer: 3 Comp # 3703

Reference:

General Electric Operator Training Services. BWR Academic Series,IIcat Transfer and Fluid Flow RWO, Sept. 85, Chapter 6, pp. 656a - 6 59a

47. Given a sudden stop in a fluid flow in a piping system due to rapid closure of an outlet valve, which one of the following terms best describes the pressure change in the system?

1.

Cavitation 2.

Shutoff head i

3.

Water hammer 4.

Pipe whip j

i l

Acc: NRC185 Rubric (s): 293006Kl.08 Cortret Answer: 3 Comp # 4112

Reference:

General Electric BWR Academics Series, IIcat Transfer and Fluid Flow,1985, pp. 696.

1

48. Which of the following statements concerning the pump law, as applied to centrifugal pumps, is corr.ct?

1 1.

Pump head is directly proportional to speed 2.

Power varies as the square of the speed 3.

Pump head varies as the square of the speed 4.

Capacity varies as the cube of the speed 1

)

1 i

+

l I

9/88

NRC Exam - Form 6470101 Acc: NRC03 Rubric (s): 2930071.06 Cerr:ct Answer: 4 Comp # 3928

Reference:

Westinghouse Hermal Ilydraulic Principle and Applications, ch. 5, pp. 20 - 21.

OUESTION 49 REFERS TO TIIE FOLLOWING INFORMATIONt Given the following information:

- heat-trancier rate (Btu /hr)

M - mass flow rate (Ib/hr) 2 A = cross sectional area (ft )

Ah - enthalpy difference (Bru/lb)

AT - temperature difference ('F) 2 U = overall heat transfer coefficient (Btu /hr-ft _sy)

Cp - specific heat at constant pressure (Bru/lb *F) h - enthalpy of fluid (Btu /lb)

49. Which one of the followhg formulas is most representative of the heat transfer rate across the tubes of a heat exchanger?

1.

= $1(Ah) 2.

- hA( AT) 3.

- NiCp(AT) 4.

O - UA( AT) l Acc: NRC158 Rubric (s): 293004Kl.13 Correct Answer: 4 d

Comp # 3525

Reference:

Brunswick Steam Electric Plant, IIcat Transfer, Chapter 8, nace. 8-45.

50. Which of the following effects will an increase in main condenser vacuum (lower absolute pressure) have on the plant?

4 1.

Increase in condenser temperature 2.

Increase la the amount of noncondensable gas in the condenser 3

3.

Decrease in main turbine efficiency 4.

Increase in condensate subcooling a

I i

, 9/88

i i

NRC Extm - Form 6470201 i

Acc: NRC80 Rubric (s): 291001K1.12 Corrset Answer: 1 Comp # 3966

Reference:

NMP-2 BWR Academics, Heat Transfer and Muld How, T. Meadows, February 1985, p. 6-39.

1.

For throttling, globe valves are preferred over gate valves because:

1.

the loss coefficient is generally more linear for globe valves than for gate valves.

l

1. the loss coefficient for a full open gbbe valve is smaller than the loss coefficient for a full open gate valve.

3. valve position indication for a midpositioned valve is more reliable for globe valves than for gate valves.

4.

valve motor operators are more adaptable to globe valves than to gate valves.

Acc: NRC225 Rubric (s): 291004K1.17 Corrtet Answer: 4 Comp # 3956

Reference:

General Electric BWR Academics Series Heat Transfer and Fluid How,1985, p. 6-89.

2.

Operating a positive displacement pump with insufficient net positive suction head will cause which one of the following to occur?

1.

Slip 2.

Decreased pump speed 3.

Viscosity loss 4.

Vapor binding Acc: NRC88 Rubric (s): 291004K1.06 i

Comet Answer: 1 Comp # 3618 l

l

Reference:

NMP-2 BWR Academics, Heat Transfer and Ruid Mow, T. Meadows, February 1985, pp. 6-76 through 6-81.

3.

Which one of the following will be most likely to increase reactor recirculation pump available net j

positive suction head?

5 1.

Loss of feedwater heating while at 80% power i

2.

Increase in icactor coolant temperature from 100*F to 200*F during a reactor startup j

3.

Decrease in reactor pressure during a normal reactor shutdown q

4.

Decrease in reactor water level from the normal level to just below the low level alarm level 4

9/88

NRC Exam - Form 6470201 Acc: NRC92 Rubric (s): 291004K1.12 Correct Answer: 3 Comp # 3718

Reference:

NMP 2 BWR Academics, IIeat Transfer and Ruid How, T. Meadows, February 1985, p. 6109.

4.

Operating a motor-driven centrifugal pump under "pump runout" conditions causes:

1.

pump overheating, cavitation, and ultimately pump failure.

2.

no damage, since the pump and motor are designed to operate without failure under pump runout conditions.

3. excessive motor current to be drawn, damage to the motor windings, and ultimately motor failure.

4.

excessive motor current to be drawn, overheating of pump and motor bearings, and ultimately pump failure.

Acc: NRC85 Rubric (s): 291002K1.15 Correct Answer: 1 Comp # 3938 Refsrence: NRC Systems Manual BWRs, BWR/6 Design, Vol. I, Chapter 3, pp. 3.112 and 3.113. *. ark's Stsndard llandbook for Mechanical Engineers, Eighth Edition, p.16-13.

5.

A correct statement regarding thermocouples is that they:

1.

will indicate low offscale with an open circuit.

2.

are more accurate than resistance temperature detectors.

3.

are made up of two similar metals in contact at one end, called the hot junction.

j 4.

are based on the inherent characteristic of metals that results in a change in electrical resistance j

with a change in temperature.

I Acc: NRC3%

Rubric (s): 291005K1.08 Correct Answer: 1

Reference:

General Electric BWR Academics Series 1985, Electrical Science, AC Generatore, and Motors.

i 6.

Generator excitation controls the megavar loading and power factor of generators operating synchronlied to a grid. Which of the following characteristics will an underexcited generator exhibit?

1.

Negative megavars and a leading power factor 2.

Positive megavars and a leading power factor 3.

Positive megavars and a lagging power factor j

4.

Negative megavars and a lagging power factor I

i i

I l

f i

l i

l 9/88 t

I

i

+

j.

NRC Exam - Fcrm 6470201 Acc: NRC411 Rubric (s): 291008K1.08

!, Correct Answer: 2

Reference:

River Bend Station, License Operator Training Manual,1987 (LOTM 10) Main Generator, p.

29.

7.

Closing a circuit breaker between two electrical generating systems that are out of phase will result in:

j

1. negating the reverse power protection on the lagging frequency system.

4

2. a rapid phase alignment which could damage generators and loads connected to the system.

1

3. a voltage reduction in both generating systems.

4.

reduction of the frequency of the combined generating system.

Acc: NRC414 Rubric (s): 291002K1,09 l

Correct Answer: 3

Reference:

BWR Training Guide, Muld Dynamics, Section 3,1970.

i 1

8.

Reactor feedwater now and vessel level detectors use differential pressure (D/P) cells to measure flow

]

and level. If a level D/P cell diaphragm fails, the level indication:

i 1

will se to 0.

l 1

2. will slowly move to 50% (midrange).

3. will indicate 100% (full range).

s 4.

remains the same.

i Acc: NRC104 Rubric (s): 291006K1.01 i

Correct Answer: 2 Comp # 3916 l

i Referene e: NRC Systems Manu-l BWRs, BWR/6 Design, Vol. 2, Chapter 10, p.10.4-14.

1 I

j 9.

As steam (shell) and liquid (tube) heat exchangers are put into service, the:

i i

j 1.

steam side is valved in before the water side to minimize scale beildup on the heat exchanger J

tubes.

j

2. water side is valved in before the steam side to prevent thermal shock from occurring.

I

3. water side i valved in before the steam side to ensure adequate venting.

j 4.

steam side is valved in before the water side to ensure that the cooldown rate does not exceed i

j design limits.

)

j Acc: NRC229 Rubric (s): 291006Kl.18 i

Corrtet Answer: 1 i

Comp # 3912 i

Reference:

General Electric BWR Academics Series liest Transfer and Fluid Flow,1985, pp. 7-28 to 7 29,

10. Proper venting of a shell and tube heat exchanger is important because:

i 1.

air is a good insulator and has a poor heat transfer coefficient, j

2.

the air bubble hinders the flow of cooling water.

3. the air bubble will cause thermal shock as it moves through the heat exchanger.

['

4.

the air bubble will cause corrosion in the heat exchanger.

! 9/88

NRC Exan Form 6470201 Acc: NRC96 Rubric (s): 291005K1.05 Correct Answer: 3 Comp # 3655

Reference:

NMP 2 BWR Academics, IIcat Transfer and Ruid Flow, T. Meadows, February 1985, p. 6108.

i

11. The average starting current for an alternating current motor that provides power for a pump is approximately:

1.

the same as its normal running current 2.

two times its normal running current 3.

five times its normal running current 4.

ten times its normal running current Acc: NRC90 Rubric (s): 291004K1.04 Correct Answer: 2 i

Comp # 3702 Ref rence: NMP 2 BWR Academics, lleat Transfer and Ruid Row, T. Meadows, February 1985, p. 6-108.

i i

12. Operating a motor-driven centrifugal pump for extended periods of time with the discharge valve shut will result in:

4 1.

no damage, since the pump and motor are designed to operate with the discharge valve shut.

2.

the pump overheating, cavitation, and ultimately pump failure, j

3. excessive motor current, damage to motor windings, and ultimately motor failure, j

4.

pump and motor overspeeding and tripping on high motor current.

l i

Acc: NRC394 Rubric (s): 291003Kl.06 i

Correct Answer: 4 l

Reference:

NNeco Training Dept. Unit No.1, Lesson Plan,1338, Emergency Diesel Gen :rator, p.13.

13. A correct statement regarding the function of a governor on an emergency diesel generator is that it:

i 1.

trips the diesel in the event of engine overspeed.

j 2.

regulates the amount of fuel supplied to the engine, to increase engine speed as load increases, t

3.

maintains generator output voltage and frequency constant as the load changes.

l 4.

regulates the amount of fuel supplied to the engine, to produce a nearly constant engine speed as

)

load changes.

l L

1 1

4 I

I

! 9/88 t

NRC Exam - Form 6470201 Acc: NRC83 Rubric (s): 291002K1.01 Correct Answer:1 Comp # 3935

Reference:

NMP 2 BWR Academics, IIcat Transfer and Fluid Flow, T. Meadows, February 1985, pp. 6-67 and 6 70.

14. A correct statement concerning a Venturi How device is that it:

1

]

1.

develops an output signal b) measuring the differential pressure of the fluid as it passes through the device.

2.

can measure the rate of tiow of incompressible fluids, but not of compressible fluids.

j

3. develops an output signal by measuring the velocity of the fluid as it passes through the device.

4.

has head losses seater than the head losses produced by an orifice.

I j

Acc: NRC373 Rubric (s): 291002K1.07 j

Correct Answer: 3 j

Reference:

GE BWR Academic Series on Instruments and Control (November 1984) pp. 2 30, fig. 2 26.

l

15. Which of the fo!!owing parameters determines the maximum level that can be indicated by a reactor water level instrument?

r

1. The elevation of t'., differential pressure cell in relation to the auxi'iary condensing chamber l

2.

The elevation of the re%rence leg condensing chamber t

3.

The level at which the reference leg penetrates the reactor vessel j

4.

He level at which the variable leg penetrates the reactor vessel 1

Q t

t 1

i i

4 l

1 i

l i 9/88 l

NRC Exan Form 6470201 Acc: NRC389 Rubric (s): 291003K1.03

. Corrtet Answer: 2

Reference:

NNECo Training Dept Unit No.1 Lesson Plan 1337 Automatic Pressure Relief (APR) System Fig 7 2, p.12.

QUESTION 16 REFERS TO THE FOLLOWING DIAGRAM:

High Drywell Pressure Low Reactor l

)

Water Level I

a l

I I

i 1

I I

O I

Push Button i

Roset l

g i

1 l

s.ai-in i

p___j

{'*

p_R31gy_,,l gm o*y p

16. The purpose of the seal in relay is to:

1.

hold the valve open even if the reset pushbutten is pressed, j

2.

hold the valve open even if the initiating conditions reset.

3.

close the valve as soon as either initiating condition resets.

4.

close the valve only when both initiating conditions reset.

\\

d I

1

< 9/88

NRC Exam - Form 6470201 l

Acc: NRC99 Rubric (s): 291007Kl.03 I

Correct Answer: 3 4

Comp # 3904

Reference:

NRC Systems Manual BWRs, BWR/6 Design, Vol. I, Chapter 2, pp. 2.61 and 2.8-1.

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

l 1.

results L-lower fuel temperature, which increases the nuclear fuel cycle efficiency.

l 2.

is controlled by complying with core thermal limits.

3.

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

4.

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

4 L

l Acc: NRC372 Rubric (s): 291002K1.07 a

Correct Answer: 1 4

l Rsference: GE BWR Academic Series on Instrument and Controls (November 1984) p. 2-30,

18. Many reactor water-level instruments are designed with a condensing chamber in the reference leg.

The purpose of the condensing chamber is to:

t 1.

keep the reference leg filled by condensing steam.

2.

provide pressure compensation for the reactor pressure exerted on the variable leg.

3.

prevent reference leg flashirg during a rapid depressurization of the reactor vessel.

4.

alleviate the need for density compensation by keeping the reference leg temperature close to the

)

temperature of the variable leg.

l l

Acc: NRC401 Rubric (s): 291001K1.01 l

Correct Answer: 2 1

4 i

Reference:

River Bend, Licensed Operator Training Manual,1987, Main Steam, pp. 7-4.

?

19. Safety valves are used in BWR nuc! car main steam systems to protect the reactor and the system i

piping from damage due to overpressurization. Which of the following statements coacerning the f

j operation of safety valves is correct?

i 1.

When the activating pressure for a safety valve returns to the lifting set point, a combination of air l

l and steam pressure above the valve disk closes the valve.

2.

As reactor pressure inercases to the safety set point, the pressure overcomes spring tension on the valve operator, causing the valve to open.

i 3.

As the disk on a safety valve lifts, less pressure is exerted on the disk, reducing the upward force on the disk, preventing "valve slamming".

4.

A safety valve is lifted off its seat, then is forced fully open by an air operated piston.

i i

l 1

j 9/88

NRC Frm - Fcrm 6470201 Acc: NRC406 Rubric (s): 291008K1.05

>. Correct Answer: 2

Reference:

Commonwealth Edison Company, Power Plant Electrical Fundamentals Book 5,1979, Section 4,

p. 68.

20. Thermal overload devices are used to protect circuits in nominal overload conditions. Which of the following defines a thermal overload device?

1.

A balanced circuit that compares normal current to a fixed overcurrent; exceeding the normal current trips the overcurrent relay.

2.

An in-line thermal coil that, when subjected to a high current, overheats and actuates a circuit-interrupting device.

t

3. A temperature monitor that senses the temperature of the operating equipment and trips the circuit breaker if the temperature exceeds preset limits.

4.

An induction coil that generates a secondary current proportional to the primary current, closing the trip circuit contacts.

Acc: NRC54 Rubric (s): 2910071.04 Corrtet Answer: 2 O

Comp # 4029

Reference:

General Electric BWR Academics Series Chemistry,1985, pp. 5 - 15.

21. A correct statement regarding a condensate demineralizer is that its efficiency can be determined by:

1.

performing a chemical analysis on the outlet of the demineralizer to detect silicate.

l 2.

sampling the inlet and outlet of the demineralizer to determine the change in conductivity.

3. sampling the inlet and outlet of the demineralizer to detect a difference in radioactivity.

4.

monitoring the change in differential pressure across the demineralizer.

Acc: NRC87 Rubric (s): 291002K1.02 1

Correct Answer: 1 l

Comp # 3960 Refer:nce: NMP 2 BWR Academics, IIcat Transfer and Fluid, T. Meadows, February 1985, pp. 6-66 and 6-68.

I

22. A correct statement regarding the use of an orifice to measure the volume flow rate of water in a pipe is that:

l 1.

the measured flow rate will be higher than the actual flow rate if the water temperature is lower j

than the calibrated temperature.

.i 2.

temperature compensation is not required to obtain accurate flow rates because water is an j

incompressible fluid.

3. the measured flow rate will be lower than the actual flow rate if the water temperature is lower than the calibrated temperature.

4.

temperature compensation is not required because the pressure drop across the orifice is a viscous effect and is 'not temperature-dependent.

l

, 9/88

NRC Ex:m - Fcrm 6470201 Acc: NRC109 Rubric (s): 292002K1.08 i, Cerrect Answer: 1 l

Comp # 4005 l

Reference:

General Physics Corp., Academic Program for Nucler Power Plant Personnel, Volume II, Physics, Chapter 4, p. 4 - 54.

j

23. A reactor with a K,, of 1.002 would be considered:

I 6

1.

supercritical

2. critical 3.

suberitical 4.

prompt critical i

Acc: NRC254 Rubric (s): 29200$K1.04 Cenect Answer: 4 Comp # 3613

Reference:

General Electric BWR Academics Series Reactor neory,1984, p. 545.

f

24. De "reverse power eNect" or "reverse reactivity eNect" occasionally observed when a shallow control l

rod is withdrawn one or two notches is due to a relatively:

j i

1.

large local power increase being onset by a moderator temperature related power decrease.

2.

small local power decrease due to the "shadowing" efect of nearby control rods.

3.

smalllocal power decrease due to increased local Doppler eNects.

t 4.

large local power increase being onset by a void related power d ' crease.

l Acc: NRC76 Rabric(s): 292006K1.22 Correct Answer: 2 i

Comp # 3474

Reference:

Georgia Power Training Manual Plant, E.I. liatch Revi, pp. 10.1.6 10, 10.1.6 11.

25. In regard to menon and samarium concentrations following a scram from extended operation at high power, which one of the following statements is correct?

1.

Xenon concentration increases for the 6rst 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, while samarium concentration decreases.

j 2.

Xenon and samarium concentrations increase for the first 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

i

3. Xenon concentration increases, while samarium concentration remains at equilibrium.

4.

Xenon concentration decreases, while samarium concentration remains at equilibrium.

j i

t I

. 9/88

NRC Exam - Form 6470201 Acc: NRC305 Rubric (s): 292008K1.20

. Correct Answer: 2 Corrp # 4010

Reference:

General Electric BWR Academics Series, Reactor neory,1984, pp. 4 5 to 5-10.

26. A power increase is initiated by an increase in recirculation flow, causing voids to be. wept away and adding positive reactivity. Which of the following statements best describes the response of the reactivity coefficients?

1.

Increasing fuel temperature implies more heat transfer to the coolant. Increased moderator temperature causes more void formation, and power stabilizes at a new hisher level.

2.

Increasing fuel temperature implies more heat transfer to the coolant, thus increasing steam generation, ne increased void fraction and fuel temperature add negative AK/K, and power stabilizes at a new higher level.

3. Increasing fuel temperature implies more heat transfer to the coolant, thus increasing steam generation, he increased steam generation raises reactor pressure and moderator temperature, offsetting the decreased volds, and power stabilizes at a new higher level.

4.

Increased moderator and fuel temperature stabilize power at a new higher level.

Acc: NRC153 Rubric (s): 292003K1.08 Correct Answer: 3 Comp # 3531

Reference:

Introduction to Nuclear Reactor Operations, Reactor Kinetics, Reed Robert Burn, p. 4 - 4.

27. After initial criticality, a reactor is leveled off. De source range channels are repositioned so that the count rate is 100 cps. Sufficient positive reactivity is added to establish a 120-second period. Which of the following indicates the time it will take for the count rate to increase to 10,000 cps with no additional action?

1.

1.2 minutes i

2.

4 minutes i

3. 9.21 minutes i

4.

15.82 minutes i

Acc: NRC145 Rubric (s): 292004K1.01 Correct Answer '

Comp # 3594 Rsferznce: Brunswick Steam Electric Plant, Reactor neory, Chapter 14, p.164.

28. "he change in reactivity produced by a unit change in reactor coolant temperature" defines which of the following reactivity coefficients?

1 1.

Void

2. Moderator

3. Power 4.

Doppler 9/88

NRC Exam - F rm 6470201 Acc: NRC175 Rubric (s): 292008K1.04

', Cctreet Answer: 2 Ccmp # 4066 Refer:nce: General Electric BWR Academics Series Recto." neory 1984, pp. 7-6

29. During reactor startup, which of the following does not affect critical rod position?

~

1.

Control rod worth 2.

Source range initial count rate

3. Fuel temperature 4.

Core age Acc: NRC261 Rubric (s): 292005K1.10 Correct Answer: 1 Comp # 3977

Reference:

General Electric BWR Academics Soies Reactor Theory,1984, p. 5-21.

I

30. Which one of the following is the best reason for "flux shaping"?

I

1. To mini'nize the potential of moving high-worth control rods v

2.

To allow thermal leakage to control thermal power by keeping periphery control rods farther out of the core

3. To equalize wear and required maintenance 4.

To reduce thermal leakage by keeping periphery control rods farther into the core Acc: NRC251 Rubric (s): 292003K1.01 Correct Answer:1 Comp # 4027 Refer:nce: General Electric BWR Academics Series Reactor Deory,1984, pp. 3 5 to 3-12.

i

31. Of the following conditions, which three are necessary for suberitical multiplication to occur?

l 1.

Neutron source, moderator, and fissionable material

]

2.

K,c,less than one, moderator, and control rods

3. Moderator, neutron source, and K,,less than one j

4.

Fissionable material, moderator, and K,, greater than one 1

l f

i

• 9/88

NRC Exam - Fcrm 6470201 Acc: NRC59 Rubric (s): 2920021.11

. Ccrrect Answer: 4 Comp # 4025

Reference:

General Electric BWR Academics Series, Reactor Theory,1984, pp.1 - 38.

l

32. Which one of the following terms is defined as the fractional change in neutron population from one generation to the next?

1.

AK 2.

K,,

3.

K,,-t 4.

Reactivity Acc: NRC182 Rubric (s): 292008K1.03 Correct Answer: 2 Comp # 4109

Reference:

General Electric PWR Academics Series, Reactor neory 1984, pp. 7 7.

i l

33. Assume your. reactor is being taken critical by periodically withdrawing equal reactivity control rod increments. Which of the following statements is correct as K,, approaches unity?

1.

The neutron level change for successive rod increment pulls becomes smaller.

2.

A longer period of time is required to reach the equilibrium neutron level after each rod withdrawal.

3.

A rod withdrawal will result in the reactor bccoming slightly supercritical, due to a "prompt jump", and then return to a suberiticallevel.

If the rod withdrawal is stopped for several hours, the neutron level will decrease to source level.

i Acc: i 042 Rubric (s): 2920081.19 Corrtet Answer: 2 Comp # 3933 i

i

Reference:

Brunswick, Steam Electric Plant, Reactor Theory, ch.14, p.190.

l

34. Assume a BWR plant is at 20% power. Power is increased to 30% by control rod withdrawal. Which

]

one of the following statements best describes the change in void fraction?

1.

Void fraction initially decreases, then linearly increases with rod worth increase.

1 2.

Void fraction increases.

]

3.

Void fraction decreases.

4.

Void fraction remains the same.

I l

i

, 9/83

NRC Exam - Form 6470201 Aec: NRC56 Rubric (s): 2920011.02 i

Correct Answer: 3 Comp # 4001,

Reference:

General Electric BWR Academics Series, Rector Theory,1984, pp. 3 - 21.

i

35. Which one of the following is the best definition of the term prompt neutron?

1.

A high-energy neutron emitted from a neutron precursor, immediately after the fission process, 2.

A neutron with an energy level greater than 0.1 MeV, emitted in less than 10-4 seconds following a nuclear fission.

I 3.

A neutron emitted in less than 10-H seconds following a nuclear fission.

4.

A neutron emitted as a result of a gamma n or alpha n reaction.

j Acc: NRC114 Rubric (s): 2920(;6Kl.11 Correct Answer: 1 Comp # 3990 1

l Rsference: General Physics Corp., Academic Program for Nuclear Power Plant Personnel, Volume II, Physics, Chapter 5, p. 5 55 56.

l j

36. A power reactor has been operating at 50% power for 4 days. Power is then increased to 100% over a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. Which of the following expresses the time range during which tue minimum concentration of xenon is expected to occur after the power increase?

I 1.

4 - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 2.

10 - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i

3.

15 - 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> t

]

4.

19 - 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> l

Acc: NRC158 Rubric (s): 293004K1.13 1

Correct Answer: 4

]

Comp # 3525 I

l

Reference:

Brunswick Steam Electric Plant, !! cat Transfer, Chapter 8, page 845.

i 3% Which of the following effects will an increase in main condenser vacuum (lower absolute pressure)

I have on the plant?

l

~

l 1.

Increase in condenser temperature I

2.

Increase in the amount of noncondensable gas la the condenser l

3.

Decrease in main turbine efficiency j

4.

Increase in condensate subcooling I

l 1

j 4

I j 9/88

) - -...

I*

NRC Exam - Fcrm 6470201 Ace: NRC03 Rubric (s'): 2930071.05 Correct Answer: 4 Comp # 3928

Reference:

Westinghouse Thermal llydraulic Principle and Applications, ch. 5, pp. 20 - 21.

QUESTION 38 REFERS TO TIIE FOLLOWING INFORMATION:

Given the following information:

- heat transfer rate (Btu /hr)

N1 = mass flow rate (Ib/hr) 2 A - cross-sectional area (ft )

l Ah - enthalpy difference (Btu /lb) 1 AT - temperature difference ('F) 2 j

U - overall heat transfer coefficient (8tu/hi-ft _ p) l Cp - specific heat at constant pressure (Bru/lb 'F) h - enthalpy of fluid (Btu /lb)

38. Which one of the following formulas is most representative of the heat transfer rate across the tubes of j

a heat exchanger?

1.

=Nf(Ah) 2.

-hA(AT) l 3.

O - MCp( AT) l 4.

O - UA(AT) l l

Acc: NRC185 Rubric (s): 293006Kl.08 i

Correct An wer: 3 l

Camp # 4112 f

Reftrznce: General Electric BWR Academics Series, IIcat Transfer and Fluid Flow,1985, pp. 6-96.

39. Which of the following statements concerning the pump law, as applied to centrifugal pumps, is correct?

4 l

1.

Pump head is directly proportional to speed 2.

Power varies as the square of the speed 3.

Pump head varies as the square of the speed 4.

Capacity varies as the cube of the speed i

1 I

i I

i l

l l

1 9/88

NRC Exam Fcrm 6470201 Acc: NRC128 Rubric (s): 293006K1.05 Correct Answer: 3 Comp # 3703

Reference:

General Electric Operator Training S.:rvices. BWR Academic Series,llent Transfer and fluid Flow RWO, Sept. 85, Chapter 6, pp. 6 56a - 6 59a

40. Given a sudden stop in a fluid flow in a piping system due to rapid closure of an outlet valve, which one of the follo ving terms best desenbes the pressure change in the system?

1.

Cavitation 2.

Shutoff head 3.

Water hammer 4.

Pipe whip Acc: NRC49 Rubric (s): 2930051.05 Correct Arewer: 2 Comp # ?)68 Referrace: Bruaswick, Steam Electric Plant, Ileat Transfer, ch. 6, p. 70.

41. Given a BWR steam cycle, which of the following is the mcst probable locat'.on for superheated, stenm?

1.

The outlet of the high pressure turbine 2.

The outlet of the moistu:e separators /rehesters

3. The inlet of tbc high pressure turbine 4.

The outlet of the low pressure turbine Acc: NRC26 Rubric (s): 2930091.10 Correct Answer: 4 Comp # 4040 Ref:rence: Brunswick Steam Electric Plant, llent Transfer, ch. 9, p. 70.

42. Which of the following thermal limits protects the fuel fron. seaching 2200*F following a loss of coolant accident (LOCA)?

1.

1.inear heat generation rate (l.IIGR)

2. Total peaking factor 3.

Maximum thermal power 4.

Average planar linear heat generation rate (APLilGR)

. 9/88

i NRC Ex:m Form 6470201 l

Acc: NRC209 Rubric (s): 293007Kl.13 Correct Answer: 3 Comp # 3510

(

l i

Reference:

Georgia Power Nuclear Training Manual; Trainirq Lesson Plan Cycle Efficiency and the Rent L

l Cycle,1985, pp.11 - 15.

I 1

43. In regard to conducting a reactor heat balance, which one of the following statements about

]

determining reactor powr.r is true?

I 1.

If the feedwater flow rate used in the heat balance calculation was lower than the actual feedwater j

ilow rate, then the actual power is higher than the currently calculated power.

2.

If the reactor recirculation pump heat input used in the heat balance calculation was omitted, then the actual power is higher than the currently calculated power,

3. If the steam flow used in the heat balance calculation was lower than the actual steam flow, then t

the actual power is higher than she currently calculated power.

l 4.

If the reactor water cleanup unit (RWCU) return temperature used in the heat balance calculation was lower than the actual RWCU return temperature, then the actual power is higher than the j

currently calculated power.

1 1

Acc: NRC148 Rubric (s): 293009K1.17 Correct Answer: 2 Comp # 3548 l

Reference:

Nuclear Power Plant Thermal Sciences, Reactor llent Generation, Reed Robert Burn, Chapter 10, p.10 - 6.

44. "The fuel bundle power that would cause the onset of transition boiling at some point in the fuel bundle" is the best definition of which of the following terms?

1.

Maximum core power j

2.

Critical power J

3. Maximum fraction of limiting power density 4.

Maximum power density 1

I Acc: NRC312 Rubric (s): 29300SK1.34 j

Correct Answer: 1 j

Comp # 3533 j

]

Reference:

General Electric IlWR Academics Series, IIcat Transfer and Huld Row,1985, p. 8-56.

l j

45. Natural circulation is inherent in a boiling water reactor (HWR). Which one of the following i

statements best describes natural circuletion after a loss of offsite power?

1.

Liquid density in the downcomer and reduction of density in the core region support the cycle.

J 2.

Two phase flow in the separators allows steam to be removed and liquid to return to the l

downcomer region.

1 3.

Relief and safety valves provide a heat sink for dect,y heat. In spite of leakage, control rod drives i

are adequate to maintain inventory,

)

4.

Dt;nsity of liquid in the core region increases, thereby allowing liquid in the downcomer to enter j

the core.

I

! 9/88 i

. -.. = _. - -.

i.

NRC Exam - Ferm 6470201 1

Acc: NRC09 Rubric (s): 2930081.07

. Correct Answer: 1 i

Comp # 4015 l

j

Reference:

Westinghouse Thermal Ilydraulic Principles and Applications, ch. 3, p. 59.

l t

j

46. Which of the following terms most accurately refers to the boiling that results when the ricam bubbles l

moving away from a heated surface collapse in the bulk fluid?

l l-l 1.

Subcooled nucleate boiling 2.

Saturated convection l

l 3.

Subcooled convection i

4.

Saturated nucleate boiling i

j Acc: NRC06 Rubric (s): 2930081.23 Correct Answer: 4

]

Comp # 3645

)

Ref:rence: Westinghouse Thermal Dynamic Principles and Applications, ch. 7, pp.13 14, Steam Tables j

Mollier Diagram.

1 E

I

47. Which of the following values most occurately represents the quality of steam leaving a cyclone l

separator at 985 psig and 1183 Btu /lb?

I J

1, 95 %

2.

)

3. 97 %

4.

99 %

l I

s Acc: NRC221 Rubric (s): 293003K1.23 Correct Answer: 4 i

i Comp # 3939 l

i i

Refer:nce: Steam Tables.

I l

48. A recently calibrated pressure gauge sensing in the same area as a temperature instrument indicates l

350 psig. Assuming saturation conditions, which one of the following will the temperature instrument l

show?

1 l

1.

420'F i

2.

425'F j

3. 430'F l

4.

435'F l

1 i

i i

i 3

l 3

l i

i 9/88 4

NRC Exam - Form 6470201 l

)

Acc: NRC169 Rubric (s): 2127:U.01

!. Ccrrect Answer: 4 t

Comp # 3468 1

Reference:

Brunswick Steam Electric Plant, IIcat Transfer, Charter 8, page 8-2 i

49. Which of the following methods of heat transfer is dc6ned by "the exchange of energy between bodies j

by electromagnetic waves through an intervening space"?

i l

1.

Conduction i

2.

Convection

3. Electrokinetics i

]

4.

Radiation 1

I Acc: NRC162 Rubric (s): 293009K1.21 i

Cert:ct Answer: 2 i

Comp # 3505

Reference:

IIcat Transfer and Ruid Row, BWR Academics Series, General Electric, Chapter 9, page 915a 1

50. Which of the following limits or conditions is evolded by maintaining the minimum critled power ratio 3

(MCPR) within speel6ed values?

1.

1% plastic strain on cladding l

2.

99.9% of the fuel pins in the core not experiencing transition boiling during a transient

3. Gross cladding failure due to lack of cooling l

4.

Fuel cladding cracking due to high stress t

i e

I I

i i

i l

1 i

l i

1 i

1 i

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l 18 -

9/88

...--.--.-l

.s t

l Docket No.

50-259 Mr.

C. T. Dexter r

Browns Ferry Nuclear Power Plant Training and Visitor Center P. O. Box 2000 Decatur, Alabama 35602 I

Dear Mr. Dexter,

l On September 21, 1988, the NRC administered a Generic Funda-4 mentals pilot examination to employees of your facility.

Enclosed with this letter are the grading and answer sheets for these examinations.

You are requested to forward these results l

to the examinees along with copies of their answer sheets.

A "CR" in the column labeled Final Grade indicates a passing grade l

for this examination.

t

]

If a candidate for an operator or a senior operator license l

[

decides to substitute the results of this examination for the l

first section of the site specific examination, he or she must

)

j request a valver of this section of the examination on his or l

i her NRC form 398.

If no waiver is requested the candidate vill l

be required to take the entire site specific examination.

For

[

candidates requesting a valver, the results of the pilot examin-i ation will be totaled with the other sections of the site speci-(

fic examination to obtair,an overall examination score.

If an i

applicant for either an RO or SRO license takes the current four section examination, the pilot examination results will count i

for 25% of the total, and if the candidate ta'nes the new three section examination it will count for 25 % for the overall operator examination score or 24 % for the overall senior oper-ater examination score.

The passing grade for an NRC adminis-l tered licensing examination is P0%, includino the fundamentals i

i section.

Passing Grade for the rundamentals Section is 70%.

I

{

In accordance with 10 CFR 2.790 of the Commission's Regulations, a copy of this letter and enclosures (1) and (2) will be placed 3

in the Public Documents Room.

The resulta for individual exam-iness are exempt from disclosure, therefore enclocures (5) and (6) vill not be placed in NRC's Public Document Room.

i i

i l

In order to better evaluate this pilot examination and improve the design of our future examinatioas, we have included with this letter voluntary Feedback Forms for both the examinees and thc training personnel and voluntary Background Information forms for candidatos at your facility.

Because of the pilot nature of this examination, we request that you take the time to return them with your evaluations.

This request was approved by the Office of Managemenu and Budget under clearance number 3150-0090.

Clearance 3150-0090 expires November 30, 1988.

Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Manage-ment, Room 3208, New Executive Office Building, Washington DC 20503.

Should you have any questions concerning this examination, please contact Mr. Paul Doyle at (301) 492-2046.

Sincerely, Kenneth E. Perkins Jr., Chief Operator Licensing Branch Division of Licensee Performance and Quality Evaluation, NRR, NRC Enclosures 1.

Examination Form "A" with answera and references 2.

Examination Form "B" with answers and references 3.

Copies of Voluntary Examination Feedback Forms concerning Pilot Examination for examinees.

4.

Copies of Voluntary Examination Feedback Forms concerning Pilet Examination for trainers.

5.

Examination Results Summary for Brovns Ferry.

6.

Copies of Ca'.didate's individual answer sheets.

t Docket No.

50-416 Mr. Oliver D. Kingsley, Jr.

System Energy Resources, Inc.

P. O.

Box 23070 Jackson, Mississippi 39225-370

Dear Mr. Kingsley,

on September 21, 1988, the NRC administered a Generic Funda-mentals pilot examination to employees of your facility.

Enclosed with this le*.ter are the grading and ansvar sheets for these examinations.

You are requested tn forward these results to the examinees along with copies of their answer sheets.

A "CR" in the column labeled Final Grade indicates a passing grade for this examination.

If a candidate for an operator or a senior operator license decides to substitute ths results of this examination for the first section of the site specific examination, he or she must request a vaiver of this section of the examination on his or her NRC form 398.

..f no vaiver is requested the candidate vill be required to take the entire nite specific examination.

For candidates requesting a valver, the results of the pilot examin-ation vill be totaled with the other asctions of the site speci-fic examination to obtain an overall examination score.

If an applicant for either an RO or SPo license takes the current four section examination, the pilot examination results vill count for 25% of the total, and if the candidate takes the new three section examination it vill count for 25 % for the overall operator examination score or 24 % for the overall senior oper-ator examination score.

The passing grade for an NRC adminis-tered licensing examination is 80%, including the fundamentals section.

Passing Grade for the rundamentals bection is 70%.

In accordance with 10 CfR 2.790 of the Commission's Regulations, a copy of this letter and enclosures (1) and (2) vill be placed in the Public Documents Room.

The results for individual exam-

)

inces are exempt from disclosure, therefore enclosures (5) and i

(6) vill not be placed in NRC's Public Document Room.

t In order to better evaluate this pilot examination and impr;ve the design or our future examinations, wr. have included with this letter voluntary Teodback Forms for both the examinees and the training personnel and voluntary Background Information forms for candidates at your facility.

Because of the pilot nature of this examination, we request that you take the timo to return then with your evaluations.

Thih request was approved by the office of Management and Budget under clearance number 3150-0090.

Clearance 3150-0090 expires November 30, 1988.

Comments on burden and duplication may be directed to the office of Management and BuGcet, Reports Manage-ment, Room 3208, New Executive office Building, Washington DC 20503.

should you have any questions concerning this examination 7 please contact Mr. Paul Doyle at (301) 492-1046.

Sincerely, Kenneth E. Perkins Jr., Chief operator Licensing Branch Division of T.icensee Performance and Quality Evaluation, NRR, NRC

Enclosures:

1.

Examination Form "A" with answers and references 2.

Examination Form "B" with answers and references 3.

Copies of Voluntary Examination Feedback Torms concerning Pilot Examination for examinees.

4.

Copies of Voluntary Examination Teodback Terms concerning Pilot Exar.ination for trainers.

5.

Examinaticn Results Summary for Grand Gulf.

6.

Copies of Candidate'u individual answer sheets.

Docket No.

50-321 Mr. H. G. Hairston III Georgia Power Company P. O.

Box 4545 Atlanta, Georgia 30308

Dear Mr. Hairston,

On September 21, 1988, the NRC administered a Generic Funda-mentals pilot examination to employees of your facility.

Inclosed with this letter are the grading and answer sheets for these examinations.

You are requested to forward thnse results to the examinees along with copies of their answer sheets.

A "CR" in the column labeled Final Grada indicates a passing grade for this examination.

If a candidate for an operator or a senior operator license decides to substitute the results of this examination for the first section of the site specific examination, he or she must request a waiver of this section of the examination on his or her NRC form 398.

If no waiver is requested the candidate Vill be required to take the entire site specific examination.

For candidates requesting a valver, the results of the pilot examin-ation will be totaled with the other sections of the site speci-fic examinatioi, to obtain an overall exanination score.

If an applicant for sicher an Ro or SRo license takes the current four section examination, the pilot examination results will count for 25% of the total, and if the candidate takes the new three section examination it will count for 25 % for the overall operator examination scora or 24 % for the overall senior oper-ator examination score.

The passing grade for an NRC adminis-tered licensing examination is 80%, including the fundamentals section.

Passing Grade for the Fundamentals Section is 70%.

In accordance with 10 CTR 2.790 of the Commission's Regulations, a copy of this letter and enclosures (1) and (2) will be placed in the Public Documents Room.

The results for individual exam-ineer are execpt from disclosure, therefore onclosures (5) and (6) will not be placed in NRC's Public Document Room.

i

l t

i 3

6 l

In order to better evaluate this pilot examination and improve the design of our future examinations, we have included with thin letter voluntary Feedback Forms for both the examineos and the training personnel and voluntary Background Information j

forms for candidates at your facility.

Because of the pilot nature of this examination, we request that you tske the time to return them with your evaluations.

4 i

This request was approved by the office of Management and Budget under clearance number 3150-0000.

Clearance 3150-0090 expires November 30, 1988.

Comments on burden and duplication may be directed to the office of Management and Budget, Reports Manage-1 t

i Kent, Room 3208, New Executive office Building, Washington DC

]

20503.

l i

t i

Should you have any questions concerning this examination' please contact Mr. Paul Doyle at (301) 492-1046.

l sincerely, l

1 I

4 1

Kenneth E. Perkins Jr., Chief

}

operator Licensing Branch Dl vision of Licensee Performance L

innd Quality Evaluation, NRR, NRC l

l Enclosurest I

l

{

1.

Examination Form "A" with answers and references i

2.

Examination Form "B" with answers and references 3.

opies of Voluntary Examination Feedback Forms concerning Pilot Examination for examinees.

j 4.

Copies of Voluntary Examination Feedback Forms i

concerning Pilot Examination for trainers, i

j 5.

Examination Results Summary for Hatch.

i i

6.

Copies of Candidate's individual answer sheats.

I i

1 i

J 4

VOILWTARY PUNDMENDIS EXAMD&TICH FEEDBACK QUESTICl@&IEE '

Pilot-@tst Participants' Form i

Name Student ID Form of Exam Ompleted (Circle One)

A B

INS'IWXTIONS We Furdamentals Exam contains 22 questions related to Omoonents,14 related to Reactor t eory, and 14 to hermodynamics. On this feedback form, you are asked to evaluate the examination questicos in each of these three areas and to answer scane general questions about the examination. It should take you about 30 to 45 minutes to ocuplete the f=hck form. Please refer to the copy of the Fundamentals Exam included in your packet of test materials to ocnplete the f=hck form. Your specific f=hek is greatly appreciated.

Please rete this form, along with the Backgrou1d Information Form, to the address previded on page 7.

Please evaluate each of the exam questions as shown in the following exanple:

I i

l Question l Single Item l

Familiar With

[Very Very l Clearly l Correct

?? ster l

Content?

l Easy Average Difficult l Stated?

l Response?

I i

i I

I I If No, ll l

l l

l

[ Yes/No l Reason l1 2 3 4 5 6 7 l Yes/No l Yes/No l

I i

1 1

Yes h

@ b, c 5 h7 hio lYesh 1

1 2 3 4 In this exa::ple, the examinee evaluated question number 1 as follows:

He was not familiar with the test content (No) because it was not covered in the training program (Reason a).

He rated the item difficult (6).

W e question is clearly s%ted (Yes).*

We question does not have a single correct response (No).

Explanations of each of these categories are prc/ided on the following page. Continued Next Page

Familiar with Content? Answer Yes if you were familiar with the question content.

that you were Dgt familiar with the content, please tell us the Reason why, using the following category codes:

a) it was not covered in your training program, b) question content is not relevant for your facility.

c) you sinply did not recall the information at the time you took the exam.

21estion Difficulty. Use the followirq definitions to rate the difficulty of each question on a 1 thrcugh 7 scale:

Very Easy = A questien that can be answered correctly by scansone who has D9%

.ompleted the fundamentals portion of the training program.

Averrge = A question that is not too easy, but not te

'ifficult.

Very Difficult = A question that cannot be answered an.ectly by scxneone who has ocmpleted the fundamentals portion of the training program.

Question Cleariv_ Stated? If an item is clearly stated, circle Yes.

If it is unclear or difficult to understand, circle No.

gimle correct Response? If there is.QDe and only one correct arswer, circle Y6s for that question. If there is no clear correct answer, or if rore than one response appears correct, please circle No.

'Ihe form for your individual question evaluations begins on the next page, followed by the general questions about the exanination.

1 Continued Next Page J

EVAIL%TIONS OF EXAMDRTION CUESTIONS l

l l Question

[ Single Item l

Familiar With Very Very l

Clearly (Correct Number l

Content?

i Easy Average Difficult l Stated?

l Response?

l l

l l

l If No, Jl l

l l

l l Yes/No l Reason l1 2 3 4 5 6 7 l

Yes/No l Yes/No l

I I

I I

l l

l l

1 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No l

l l

l 1

3 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 4

l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No l

I I

I i

5 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No 6

l Yes/No

] a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No I

i i

l I

7 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No 8

l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No i

I I

I I

9 l Yes/No l a, b, c 1 1 2 3 4 5 6 7 l

Yes/No l Yes/No 10 l Yes/No

] a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 1

i l

I I

11 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 12 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No l

l 1

l I

13 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No 14 I Yesg o l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No I

I l

I l

15 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 16 l Yes/No j a, b, c j 1 2 3 4 5 6 7 l Yes/No l Yes/No i

I I

I i

17 l Yes/No j a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No 18 l Yes/No j a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No I

I i

l I

i 19 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No 20 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No l

l l

1 I

l 21 I Yes/No 1 a, b, c I 1 2 3 4 5 6 7 l

Yes/No l Yes/No 22 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No l

I I

l l

23 l Yes/No I a, b, c l 1 2 3 4 5 6 7 Yes/No l Yes/No 24 l Yes/No I a, b, c l 1 2 3 '4 5 6 7 Yes/No l Yes/No i

I I

I 25

• l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No 26 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No l

I I

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! Continued Next Page

Evaluations of Examination Ouestions (cont'd) l l

l Question l Single Item l Familiar With lVery Very l Clearly

[ Correct Number l

Content?

l Easy Averago Difficult l Stated?

l Response?

I I

I I

l l If No, l l l

l l

l l Yes/No l Reason l1 2 3 4 5 6 7 l

Yes/No l Yes/No I

i i

l I

i I

1 i

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1 1

I I

27 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 28 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No I

l 1

I I

29 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/Ne 30 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No I

I i

l 31 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 32 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No i

l i

I i

33 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 34 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No l

l 1

I i

35 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 36 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No i

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37 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 38 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 1

i i

I I

39 l Yes/No l a, b, c ] 1 2 3 4 5 6 7 l

Yes/No l Yes/No 40 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No I

l l

I I

41 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l Yes/No l Yes/No 42 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No l

I l

l l

43 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No 44 1 Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No l

l l

l l

45 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No 46 l Yes/No j a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No I

I I

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47 l Yes/No l a, b, c l 3 2 3 4 5 6 7 l

Yes/No l Yes/No 48 l Yes/No l a, b, c l 2 3 4 5 6 7 l Yes/No l Yes/No I

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l 49 l Yes/No l a, b, c l 1 2 34 5 6 7 l Yes/No l Yes/No 50 l Yes/No l a, b, c l 1 2 3 4 5 6 7 l

Yes/No l Yes/No I

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GDIEPAL OJESTIONS ABOLTP WE FUNDAMDTTALS EXAMD&TICH In this section, we ask you to answer specific questions about each of the three sections in the exam (ccanponents, Reactor Seory, ard termo-dynamics) and s m e general questions about the exam.

For each statement appeariry below, please indicate your response by circlirg Yes or No.

If you want to provide ocar.mts about your respcnses to these items, please write them in the space below each item. You can also provide additional cerraents about the exam in the last section.

Components Ouestions fItems 1 to 22) i Yes No 1.

Do the 22 exam questions represent a good measure of basic Camponents knculedge?

Yes No 2.

Do the 22 exam questios.3 ccuprehensively sample Ctxnponents material presented in yottr training prcgram?

Reactor Reorv Questiors (Items 23 to 36)

Yes No 3.

Eb the 14 exam questions represent a good measure of basic Reactor 'Iheory knowledge?

Yes No 4.

Ib the 14 exam quesuions oceprehensively samle Reactor teory tuterial presented in your training program?

Thermcdyra"tics Ouestions (Iters 37 to 50)

Yes No 5.

Do the 14 exam questions represent a good measure of basic termodynamics knowledge?

Yes No 6.

Do the 14 exam questions acrprehersively sample termodynamics material presented in your l training program?

Yes No 7.

Is it reasonable to expect an iniividual with satisfactory knowledge of the subject areas to ocuplete the nandamentals Exam in two hours or less? Continued Next Pne;e

General Ouestions about the Fundamentals Exam (cont'd)

Yes No 8.

Should more items be a4 %i to this exam to ensure ocaprehensive coverage?

Yes No 9.

Can these knowledge areas be ocaprehensively tested with fewer items?

Yes No

10. Do you believe that it is necessary for scueone to have ocopleted all or part of the training program to obtain a score of 70% or higher on this exam?

Yes No

11. Do you think non-licensed operators currently participating in the operator training prvg am need to study to obtain a score of 70% or higher on the exam?

Yes No

12. Would you recccmerd that a passing score on this exam be required of all non-licensed operators prior to receiving an Imc license?

Yes No 13.

In general, is this exam too difficult?

(Difficult is defined as containirs rany iters that cannot be answered correctly by scoeone who has cce training program.) pleted the fundamentals portion of the Yes No 14.

In general, is this exam too easy?

(Easy is defined as con-taining rany iters that can be answered correctly by scoeone kho has agt corpleted the fundamentals portion of the training Program.)

1 Yes No 15.

Is the percentage of iters for the three sections appropriate for this exam (i.e., Oct:ponents, 44%; Reactor 'Iheory, 28%; and 1

'Ihermodynamics, 28%)?

l Yes No

16. Does this exam measure kn:Niedge required to successfully l

cceplete the Canponents, P4 actor Theory, and WTanics sections of the operator training program? Continued Next Page

Yes No

17. W s the material covered in this exam presented early in ycx1r training pnxyram?

Yes No

18. In general, do scores on this exam represent good indicators of how well an individual will perform on the job as a licensed operator?

Yes No 19.

Do you feel that your exam score Itp N ics your knowledge about the three areas?

General Cm. a ts If you have additional ocuments that ycu would like to make about the Furvhmantals Examination, please provide them below.

Thank you for your input. Please return this questionnaire, alorg with the Backgrouni Infornation Form, to:

I.en Wiens U.S. IRC Mail Stop Ch7N 10-D 18 Washington, DC 20555 _ --

o PIIur-TEST PARTICIPNTIS' BACKGRCUND INFORMATIOti FORM s

Name Student ID Form of Exam Ompleted (Circle one) A B

on this fom, we ask you to provide scue backgraind information about yourself. Please note that your participation is strictly voluntary. 'Ihe infomation you provide will be used to determine whether or not scores on the Fundamentals Examination serve as usehil indicators of operator training program experience and/or background.

'Ihis request was approved by the Office of Management and Budget under clearance number 3150-0090. Clearance number 3150-0090 expires on Nov 30, 1988. Ccraments on burtlen and duplication may be directed to the Office of Management and Budget, Reports Management, Roca 3208, New Executive Office Bldg., Washington, D.C. 20503.

v.f you have any questions about this form, please contact Mr. Ian Wiens at NRC Headquarters (phone 301-492-3171). Please mail this form, along with the Examination Faadback Questionnaire, to the address provided c.n Page 4.

'Ihe follcuing questions ask for information about ycer education, train-ing, and job experience. Please read each question and answer by circlim the one response that describes you best or filling in the blanks where indicated.

EEUCATION i

1.

What is your highuit level of education?

a.

High School GED b.

High School graduate c.

Attended Vocational-Technical school d.

Graduated frcn a Vocational-Technical school e.

Scce college course work f.

Graduate frca a two-year college pwgam g.

Graduate fren a four-year college program h.

Scne graduate course work i.

Ccs:pleted a graduate program.

1 2.

If you ccrpleted college (2-or 4-year program), please identify your major program.

I a.

Nuclear Engineering b.

Other EngineerinJ (please specify)

Ihysical Sciences (please specify) c.

d.

WJwmatics' and Oceputer Sciences e.

Other (please specify) 1 Continued Next Page

3.

If you ocupleted collego, please indicate wtwn you graduated.

s Month Year 4.

Have you taken college course (s) in nuclear energy?

(Do not include Cae licensed operator training program when answering this question.)

a.

Yes If yes, indicate the number of courses:

b.

No MILIT11<Y 'IPAINING EXPERID7CE 5.

Please indicate if you have served in a branch of the U.S. military.

Does not apply, did rd serve in a branch of the military, a.

b.

Army c.

Air Force d.

Marine Cbrps e.

Navy f.

Cbast Guard 6.

If you served in the Navy, did you work in the Nuclear Pregulsion Program?

a.

Yes If yes, iniicate how long ycu served:

Years b.

No Months 7.

If you served in the U.S Navy Nuclear Proculsion Prcaram, please answer questions A and B below.

A.

Irdicate the highest position held in the nuclear propulsion program.

a.

Propulsion Plant Watch Officer b.

Eroineering Watch Supervisor c.

Engine Ru Supervisor d.

P4 actor Operster e.

Chief, Reactor Watch f.

Ergineering Officer of Watch i

g.

Propulsion Plant Watch Supervisor j

h.

Other (please specify)

B.

Indicate the time period in which ycu served in the position identified in Item A above.

Frm:

Month Year

'Ib:

Month Year l

\\

r Continued Next Page i

l

LICENSED OPERATOR TRAINING PROGRAM EXPERIENCE 8.

Please answer questions A, B, c, and D about the licensed operator training program.

A.

Are you currently enrolled in the licensed operator program?

a.

Yes b.

No.

I have already ocupleted the program.

c.

No.

I will soon begin the training program, d.

No. I do not plan to take this training program.

B.

If you are.gprrently enrolled in the licensed operator course, please specify how nuch of the program you have empleted to date.

Weeks out of weeks for the total training p4.v,pam.

c.

If you have already ocmoleted the training program, plow indicate the date that you ocmpleted it, Month Year D.

If you clan to becrin the trainim Ehmu, please indicate when.

Month Year i

9.

Below, please answer questions about specific licensed operator i

training ocurses that you have ocupleted.

A.

Have you ccmpleted a ocurse in Peactor 'Iheory?

a.

Yes Please indicate the date ocmpleted:

Month Year i

b.

No B.

Have you ocmpleted a course in C+- d.m?

a.

Yes Please indicate the date ocupleted Month Year b.

No c.

Have you ocmpleted a courso in 'Ibemodynamics?

a.

Yes Please indicate the date empleted:

Month Year b.

No

. contimed Next Page

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

,---,__.--,r___,r.,,...,_.,y-_.,,.,--,-.-m,---.-_-.--r r--

.,_.wy,4-.

D.

If you plan to begin the training progr a, please indicate when:

i Month Year JOB EXPERIDE 10.

What is your present job?

a.

Non-licensed / auxiliary /equipnent operator b.

Reactor operator c.

Senior reactor operator d.

Sh6ft technical advisor (SIA) e.

Shift supervisor f.

Other (please speciff) 11.

How long have you or did you work as a non-licensed /nuxiliary/equipnent operator?

a.

Months Years b.

Does not apply, have never worked as a non-licensect/ auxiliary /equipnent operator.

12.

How long have you spent in your present job? Please answer this question even if it is the same as answer #11 above.

Months Years 13.

What is the total time you have worked in a cx2nmercial nuclear pcser plant?

Months Years

'Ihank you for taking the time to cxxplete this form. Please mail this, along With the Dcamination Feedback Questionnaire to:

{

Len Wiens U.S. Imc Mail Stop CHIN 10-D 18 Washington DC 20555 t _ ____,

o VOUNTARY IUNDAMDTIAIS EXAMD& TION FEEDBACK QUESTICNNAIRE Trainers' and Examiners' Form IP.me Facility / Site Did you take the Fundamentals Examination? (Circle one)

Yes No If Yes, please answer following questions:

Student.TR Exam Fom (Circle one) A B

INSTRUCTIONS S e Fundamentals Exam contains 22 questions related to Ocmoonents, 14 related to Reactor Reory, and 14 to m e h es. On this faadhack form, you are asked to evaluate the examination questions in each of these three areas and to answer sme general questions about the examination. It should take you abcut 30 to 45 minutes to emplete the faadhack fom.

Please refer to the copy of the Fundamentals Exam included in your packet of test materials to emplete the faarhek fom. Ycur srecific faarhek is greatly appreciated.

Please return this fom to the ackiress provided on page 7.

Please evaluate each of the exam questions as shown in the example below.

As a trainer or examiner, we wculd like you to consider how relevant each ques-tion is for non-licensed coerators carticioatinct in the coerator licensim traininct crocn am.

l l

l Question (Sirgle Item l

Familiar With IVery Very l Clearly ICorrect Nu:rber l

Content?

l Easy Average Difficult! Stated?

l Response?

I I

I i

l l If No, ll l

l l

l l Yes/No l Reason l1 2 3 4 5 6 7 l

Yes/No l Yes/No i

I i

l I

i I

I i

l Yes h lI @ b, 1

l1 2 3 4 5@7 l h io lYesh In this example, the trainer evaluated question number 1 as follows:

Non-licensed operators would not be familiar with the test content (No) because it is not covered in the training program (Reason a).

We item is rated as difficult (6)

We question is clearly stated (Yes).

Se question does not have a single correct response (No).

1 Explanations of each of these categories are provided on the following page. Continued Next Page

Familiar with Content?

Answer Yes if non-licensed operators participating in the cperator licensing training program would be familiar with the question i

content. If you answer No, that non-licensed couators would not be familiar with the content, please tell us the Reason why, using the following category codes:

1 a) it is not covered in the training program.

b) question content is not relevant for your facility.

Question Difficulty. Use the following definitions to rate the difficulty of i

each question on a 1 through 7 scale:

Very Easy = A question that can be answered correctly by scrneone who has Dat ccrrpleted the fundamentals portion of the training program.

Average = A question that is not too easy, but not too difficult.

Very Difficult = A question that cannot be answered correctly by scaneone who has ccurpleted the fundamentals portion of the training program.

Question Clearly Stated? If an item is clearly stated circle Yes. If it is unclear er difficult to understand, circle No.

Sinole correct Response? If there is one and only one correct answer, circle Yes for that question. If there is no clear correct answer, or if more than one response appears correct, please circle No.

The fem for your iniividual question evaluations begins on the next page, followed by the general questions about the examination.

. continued Next Page

.WAUATIONS OF IUNDAMDfIAIS DMINATICH QUESTICHS l

l l Question l Single Item l

Familiar With lVery Very l

Clearly

[ Correct Number l

Content?

l Easy Average Difficult l Stated?

l Response?

I I

I I

l l If No, il l

[

l l

l Yes/No l Reason l1 2 3 4 5 6 7 l

Yes/No l Yes/No l

I I

I I

l l

I I

I 1

l Yes/No l a, b, 11 2 3 4 5 6 7 l

Yes/No

[ Yes/No 2

l Yes/No l a, b, l1 2 3 4 5 6 7 Yes/No l Yes/No 1

i i

I 3

l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 4

l Yes/No j a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No l

I I

I I

5 l Yes/No I a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 6

l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No i

I I

I I

7 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/NG l Yes/No 8

l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No l

1 1

I I

9 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 10 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No i

1 1

I i

11 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 12 I Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No i

I I

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13 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No

[ Yes/No 14 I Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No l

I I

l l

15 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 16 l Yes/No I a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No I

I I

l l

17 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 18 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No l

l I

l l

19 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No I Yes/No 20 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No l

l l

l l

21 l Yes/No i a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 22 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No I

l l

I l

23 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 24 l Yes/No a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No I

I l

l

)

25 1 Yes/No a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 26 l Yes/No i

a, b, l1 2 3 4 5 6 7 l

Yes/Ne Yes/No l

I l

l i

. Omtinued Next Page

Evaluations of Fundanentals Exam Ouestions (cont'd) l l

l Question

[ Single Item l

Familiar With lVery Very l

Clearly (Correct Nu:rber i

Content?

l Easy Average Difficult l Stated?

l Response?

I i

l l

l If No ll l

l l

l l Yes/No l Reason l1 2 3 4 5 6 7 l

Yes/No l Yes/No I

i i

I I

I I

I I

I 27 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No j Yes/No 28 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No i

I I

I I

29 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 30 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No i

I I

I I

31 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 32 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No i

I I

I 33 l Yes/No l a, b, l1 2 3 4 5 6 7 Yes/No l Yes/No 34 l Yes/No I a, b, l1 2 3 4 5 6 7 ll Yes/No l Yes/No I

I I

I I

35 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 36 I Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/N l Yes/No I

i I

I I

37 I Yes/No l a, b,

[l 2 3 4 5 6 7 l Yes/No l Yes/No 38 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No l

I I

l l

39 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 40

) Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No i

I I

I I

41 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 42 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No I

I I

I l

43 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 44 l Yes/No I a, b, l1 2 3 4 $ 6 7 l Yes/No Yes/No l

I I

I 45 l Yes/No 1 a, b, l1 2 3 4 5 6 7 l

Yes/No L Yes/No 46 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No Yes/No l

l l

l 47 l Yes/No I a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 48 I Yes/No 1 a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No l

I I

I I

49 l Yes/No l a, b, l1 2 3 4 5 6 7 l

Yes/No l Yes/No 50 I Yes/No I a, b, j1 2 3 4 5 6 7 l Yes/No l Yes/No i

I I

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. 0:mtinued Next Page

GDIEPAL CUESTICtIS ABXTr 'IME FUNDAMDTIAIS EXAMINATICti In this section, we ask you to answer specific questions about each of the three sections in the exam (Ctanponents, Peactor 'Iheory, and 'Iherro-dynamics) arx1 scene general questions about the exam.

Scma of the following questions assume that you have deta led inforsation about the Operator Licensing Training Program.

If that is not, true, please write "Do Not 10xu" for those questions.

For each statement appearing below, please inlicate your response by circling Yes or No.

If you want to provide ccaments about your responses to these items, please write them in the space below each item. You can also provide additional ocm:ments about the exam in the last section.

Ccroonents Questions (Items 1 to 22)

Yes No 1.

Do the 22 exam questions represent a good measure of basic Ccmponents knowledge?

Yes No 2.

Do the 22 exam questions emprehensively sa::ple Cmponents material presented in your Operator Licensing Training P% ara?

Reactor 'Iheory Ouestions (Items 23 to 36)

es No 3.

Do the 14 exam questions represent a gocd measure of basic Reactor 'Iheory knowledge?

Yes No 4.

Do the 14 exam questions ocmprehensively sample Reactor 'Iheory raterial presented in your Operator Licensing Training Program?

'Ihennedynamics Questions (Iters 37 to 50)

Yes No 5.

Do the 14 exam questions represent a good measure of basic

'Ihermcdynamics knowledge?

Yes No 6.

Do the 14 exam questions ocaprehensively sanple 'Ihermcdynamics material presented in your operator Licensing Training Program?

Yes No 7.

Is it reasonable to expect an individual with satisfactory knowledge of the subject areas to ocuplete the nzndamentals Exam in two hours or less? Continued Next Page

9 General Ouestions about the Furdamentals Dcam (cont'd)

Yes No 8.

Should more items be added to this exam to ensure ccmprehensive coverage?

Yes No 9.

Can these knowledge areas be ocaprehensively tested with fewer itsias?

Yes No

10. After having reviewed this exam, do you believe that it is newn for smeone have ocmpleted all or part of the training proyram to obtain a score of 70% or higher?

Yes No

11. After having reviewed this exam, do you think non-licensed operators currently participating in the operator training program need to study to obtain a scrare of 70% or higher?

Yes No

12. Wculd you r - nd that a passing score on this exam be required of all non-licensed operators prior to receiving an NRC license?

Yes No

13. In general, is this exam too difficult?

(Difficult is defined as containing many items that cannot be answered correctly by someone who has ocupleted the furriweatals portion of the cperator training prcgram.)

Yes No

14. In general, is this exam too easy?

(Easy is d9 fined as containing many items that can be answered correctly by sceneone who has agd; ocr:pleted the fundamentals portion of the operator training program.)

Yes No

15. Is the percentage of items for the three secticos apprrpriate for this exam (i.e., Cteponents, 44%; Reactor Theory, 28%; and Thernodynamics, 28%)?

i Yes No

16. Does this exam measure knowledge required to successfully ecmplete the cetponents, Reactor Theory, and Thermodynamics sections of the operator training program?

Yes m

17. Is the mterial covered in this exam presented early in your trainin} program?

{

. continued Next Page J

s

Yes No

18. In general, do scores en this exam represent good iniicators of how well an individual will perform on the job as a licensed operator?

1 Yes No

19. Do you feel that exam scores of 70% or higher indicate that an iniividual has basic, furrhwntal knowledge of these areas?

General Crmiments If you have additional ocuments that you would like to make about the Funda-m mtals Examination, please provide them below.

?

f f

1 M you for your input. Please return this fera to:

IAn Wiens U.S. NRC Mali Stop Ch7N 10-D 18 Washington, DC 20555 1

-7 I

I u

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