Text

Forwards Results of Pilot BWR Generic Fundamentals Exam for Region Iii.Regions Delegated Authority to Grant Waivers for Candidates Requesting to Substitute Pilot Exam Scores for Fundamentals Portion of Licensing Exam
	ML20207K796
Person / Time
Issue date:	10/06/1988
From:	Perkins K; Office of Nuclear Reactor Regulation
To:	Wright G; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
	NUDOCS 8810170025
	Download: ML20207K796 (56)
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'o UNITED STATES

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g NUCLEAR REGULATORY COMMISSION

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CAsHINGTON, D. C. 206S5 k..... p OCT 0 61988 MEMORANDUM FOR:

Geoffrey C. Wright, Chief Operations Branch Division of Reactor Safety Region III FROM Kenneth E. Perkins Jr., Chief Operator Licensing Branch Division of Licensee Performance and Quality Evaluation, NRR SUIk7ECT:

RESULTS OF PILOT BWR GENERIC FUNDAMENTALS EXAMINATION FOR REGION III.

On September 21, 1988, NRC administered a pilot Generic Funda-mentals Examination for six (6) 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 the Commission's Replations, a copy of this letter and enclosures (1) through (4) will be placed in the Public Documsnts Room.

The results of individual i

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 requests the regions are delegated authority to grant waivers for candidates requesting to substitute their pilot examination 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 examination score is to be used in deter-mining the results overall results of the licensing examination.

4 If an applicant for either an RO or SRO license takes the current j

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 i

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

tj9 Passing grade for the fundamentals section is 70%.

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OCT 0 61664 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 Licensee Performance and Quality Evaluation, NRR Enclosures 1.

Examination Form "A" with answers 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 exaninees 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

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NRC Exam - Form 6470101 Acc: NRC87 Rubric (s): 291002K1.02 Correct Answer: 1 Comp # 3960 Ref:rence: NMP-2 IlWR Academics, IIcat Transfer and Ruid, T. Meado.vs, February 1985, pp. 6-66 and 6-68.

1.

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

1.

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

2.

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

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

Reference:

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

2.

A correct statement regarding a condensate demineraliz:r is that its efficiency can be determined by:

1.

performing a chemical analysis on the outlet of the demineralizer 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.

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

Reference:

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

p. 68.

3. hermal overload devices are used to protect circuits in nominal overload conditions. Which of the following defmes a thermal overload device?

1.

A balanced circuit that compares normal current to a ftxed tnercurrent; 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 operating equipment and trips the circuit breater 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. 9/88

NRC Ex:m - F::rm 6470101 Acc: NRC401 Rubric (s): 291001K1.01 Correct Answer: 2 Ref:rence: River Ilend, Licensed Opc,tator Training Manual,1987, Main Steam, pp. 7-4.

4.

Safety valves are used in llWR 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 closed 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 R:f:rence: GE IlWR Academic Series on Instrument and Controls (November 1984) p. 2 30.

5.

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

The 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 # 39M R:f:rence: NRC Systems Manual llWRs, IlWR/6 Design, Vol. I, Chapter 2, pp. 2.6-1 and 2.8-1.

6.

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

1.

results in lower fuel temperature, which increases the nuclear fuel cyc!c efficiency.

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.

1 l

9/88

NRC Exam. Form 6470101 Acc: NRC389 Rubric (s): 291003Kl.03 Correct Answer: 2

Reference:

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

I OUEST10N 7 REFERS TO TIIE FOLLOWING DIAGRAM:

High Drywell Pressure Low Reactor l

Water Level i

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Push Button i

Roset l

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me Delay j

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7.

The purpose of the scalin relay is to:

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

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.

Acc: NRC373 Rubric (s): 291002K1.07 Correct Amwer: 3 Ref::ence: GE IlWR Academic Series on Instruments and Control (November 19S4) pp. 2 30, fig. 246.

8.

Which of the following 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 cor.densing chamber

2. The elevation of the reference leg condensing chamber 3.

He level s.t which the reference leg p:netrates the reactor vessel 4.

De level at which the variable leg penetrates the reactor vessci 3

9/83

NRC Exam - F:rm 6470101 Acc: NRC83 Rubric (s): 291002K1.01 C:rrect Answer: 1 Comp # 3935

Reference:

NMP 2 BWR Academics, Ileat Transfer and Fluid Row, T. Meadows, February 1985, pp. G67 and 6 70.

9.

A cornet 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 orifice.

Acc: NRC394 Rubric (s): 291003Kl.06 Cctreet 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 dieselin the event 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.

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

Reference:

NMP-2 BWR Academics, IIcat Transfer and Ruid Flow, T. Meadows, February 1985, p. 6-103.

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.

oump and motor overspeeding and tripping on high motor current,

l. 9/88

NRC Exam - F:rm 6470101 Acc: NRC96 Rubric (s): 291005K1.05 Correct Answer: 3 Comp # 3655

Reference:

NMP-2 BWR Academics, IIcat Transfer and Muld Mow, T. Meadows, February 1985, p. 6-108.

12. 'Ihe average starting current for an alternating current motor that provides power for a pump is approximately:

1.

th: same as its normal running current 2.

two times its normal running current 7

3. five times its normal running current 4.

ten times its normal running current Acc: NRC229 Rubric (s): 291006K1.18 Cctr:ct Answer: 1 3

Comp # 3912 l

Ref:rence: General Electric BWR Academics Series IIcat Transfer and Muld Flow,1985, pp. 7 28 to 7-29, 4

i

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 coemeient.

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.

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

Corr:ct Answer: 2 Comp # 3916 i

i

Reference:

NRC Systems Manual BWRs, BWR/6 Design, Vol. 2, Chapter 10, p.10.4-14.

1

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

l 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.

J t

l l

l l 9/88

d NRC Exam - F rm 6470101 Acc: NRC414 Rubric (s): 291002K1.09

. Correct Answer: 3

Reference:

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

15. Reactor feedwater flow and vessellevel 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 Correct Answer: 2

Reference:

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

29.

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

1.

negating the reverse power protection on the 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: NRC3%

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

Reference:

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

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

l 1.

Negative megavars and a leading power factor 2.

Positive megavars and a leading power factor 3.

Positive megavars and a lagging power factor 4.

Negative megavars and a lagging power factor Aec: NRC85 Rubric (s): 291002K1.15 Correct Answer: 1 Comp # 3938 R;f::rence: NRC Systems Manual BWRs, BWR/6 Design, Vol. I, Chapter 3, pp. 3.112 and 3.113. Mark's Standard llandbook for Mcchanical Engineers, Eighth Edition, p.1613.

18. A correct statement regarding thermxouples 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.

4.

ue based on the inherent characteristic of metals that results in a change in electrical resistance with a change in temperature. 9/88

NRC Exam - Fcrm 6470101 Rubric (s): 291004K1.12 Acc: NRC92 Correct Answer: 3 Comp # 3718 RefIrence: NMP-2 DWR Academics, Ileat Transfer and Fluid How, 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.

l 3.

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

4.

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

Acc: NRC88 Rubric (s): 291004K1.%

Cctrect Answer: 1 Comp # 3618 Ref:rence: NMP-2 BWR Academics, llent Transfer and Fluid Row, T. Meadows, February 1985, pp. 6 76 l

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 2.

Increase in reactor coolant temperature from 100*F to 200'F during a reactor startup 3.

Decrease in reactor pressure during a normal reactor shutdown 4.

Dec. case in reactor water level from the normal level to just below the low level alarm level Acc: NRC225 Rubric (s): 291004K1.17 i

Correct Answer: 4 Comp # 3956 Ref:rence: General Electric BWR Academics Series IIcat Transfer and Muld How,1985, p. 6-89.

j r

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 i

3. Viscosity loss 4.

Vapor binding l

, 9/88 l

NRC Exam - Fcrm 6470101 Acc: NRC80 Rubric (s): 291001".1.12 4

Correct Answer: 1 Comp # 3966

Reference:

NMP 2 BWR Academics, IIcat Transfer and Ruid Mow, T. Meadows, February 1985, p. 6 39.

4 1

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 coemeient for a full open globe valve is sms!'er 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 rnore adaptable to globe valves than to gate valves.

Acc: NRC114 Rubric (s): 292006K1.11 Cctreet Answer: 1 Comp # 3990 I

Reference:

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

23. 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period. Which of the following expresses the time range during which the minimum concentration of xenon ic expected to occur after the power increase?

i 1.

4 - 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

2.

10 - 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.

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

19 - 21 hours2.430556e-4 days 0.00583 hours 3.472222e-5 weeks 7.9905e-6 months Acc: NRC56 Rubric (s): 2920011.02 Correct Answer: 3 Comp # 4001 4

)

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

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

1.

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

4 l

2.

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

3. A neutron emitted in less than 10-" reconds following a nuclear fission.

4.

A neutren emitted as a result of a gamma n or alpha n reaction, i

i l

, 9/88 I

NRC Exam - F:rm 6470101 Acc: NRC42 Rubric (s): 2920081.19 Correct Answer: 2 Comp # 3933 Ref:rence: Brunswick, Steam Electric Plaat, Reactor neory, ch.14, p.190.

25. 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.

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

2. Vold fraction increases.

3. Vold fraction decreases.

4.

Void fraction remains the same.

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

Reference:

General Electric BWR Academics Series, Reactor Deory 1984, pp. 7 7.

26. 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. he 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 withdiawal will result in the reactor becoming slightly supercritical, due to a "prompt jump", and then return to a suberitical level.

4.

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

Acc: NRC59 Rubric (s): 2920021.11 Cctreet Answer: 4 Comp # 4025 Ref:rence: General Electric 11WR Academics Series, Reactor neory,1984, pp.1 - 38.

27. 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 9/88

NRC Exam Form 6470101 Aec: NRC251 Rubric (s): 292003K1.01 Cctrect Answer: 1 Comp # 4027

Reference:

General Electric BWR Academics Series P.cactor Theory,1984, pp. 3-5 to 3-12.

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

1.

Neutron source, moderator, and fissionable material 2.

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

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

Fissionable material, moderator, and K,, greater than one Acc: NRC261 Rubric (s): 29200$K1.10 Cctreet Answer: 1 Comp # 3977

Reference:

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

l l

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

1. To minimize the potential of moving high worth control rods j

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 thermalleakage by keeping periphery control rods farther into the core Acc: NRC175 Rubric (s): 292008K1.04 Correct Answer: 2 Comp # 4066

Reference:

General Electric BWR 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 cosmt rate 3.

Fuel temperature 4.

Core age

. 9/88

NRC Exam - Form 6470101 Acc: NRC145 Rubric (s): 292004K1.01 Correct Answer: 2 Comp # 3594

Reference:

Brunswick Steam Electric Plant, Reactor neory, Chapter 14, p.164.

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

1.

Void 2.

Moderator 3.

Power 4.

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

Reference:

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

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

1.

1.2 minutes 2.

4 minutes

3. 9.21 minutes 4.

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

Reference:

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

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

1.

Incicasing fuel temperature implies more heat transfer to the coolant. 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. De increased void fraction and fuel temperature add negative AR/K, and power stabilizes at a new higher level.

3.

heressing fuel tetaperature implies more heat transfer to the coolant, thus increasing steam generation. De increased steam generation raises reactor pressure and moderator temperature, offsetting the dects ased voids, and power stabilizes at a new higher level.

4.

Increased moderator and fuel tempera:ure stabilire power at a new higher level. 9/c'8

NRC Exam - Fcrm 6470101 Acc: NRC76 Rubric (s): 292006K1.22 Cerrect Answer: 2 Comp # 3474

]

Reference:

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

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

i 1.

Xenon concentration increases for the first 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , while samarium concentration decreases.

~

2.

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

3.

Xenon concentration increases, while samarium concentration remains at equilibrium.

4.

Xenon concentration decreases, while samarium concentration remains at equilibrium.

Acc: NRC254 Rubric (s): 292005K1.04 Cerrect Answcr: 4 2

Comp # 3613 i

Reference:

General Electric BWR Academics Series Reactor neory,1984, p. 5-25.

35. De "reverse power cNect" or "reverse reactivity efect" occasionally observed when a shallow control rod is withdrawn one or two notches is due to a relatively:

1.

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

2.

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

3.

rmall local power decrease due to increased local Doppler eNects.

4.

large local power increase being onset by a void related power decrea:e.

I Acc: NRC109 Rubric (s): 292002K1.08 Corr:ct Answer: 1 a

Comp # 4005 1

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. suberitical 4.

prompt critical l

)

l

. 9/88

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

Reference:

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

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

1, 1% plastic strain on cladding 7.

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.

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

Reference:

Brunswick Steam Elec'ric Plant, He. Transfer, Chapter 8, page 8-2

38. Which of the following methods of heat 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 Correct Answer: 4 Comp # 3939

Reference:

Steam Tables.

39. A recently calibrated pressure gauge sensingin the same area as a temperature instrument indicates 350 psig. Assuming saturation conditions, wh:ch one of the following will the temperature instrument show?

1. 420'F 2.

425'F 3.

430*F 4.

435'F 9 9/88

NRC Exan - Form 6470101 Acc: NRC06 Rubric (s): 2930081.23 Ccrrect Answer: 4 Comp # 3645

Reference:

Westinghouse Thermal Dynamic Principles and Applications, ch. 7, pp.13 - 14, Steam Tables Mollier Diagram.

40. Which of the following values most accurately represents the quality of steam leaving a cyclone separator at 985 psig and 1183 Btu /lb?

1.

95 %

2.

3. 97 %

4.

99 %

Acc: NRC09 Rubric (s): 2930081.07 Corr:ct Answer: 1 Comp # 4015 R:ference: Westinghouse Thermal Hydraulic Principles and Applications, ch. 3, p. 59.

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

1.

Subcooled nucleate boiling 2.

Saturated convection 3.

Subcooled convection 4.

Saturated nucleate boiling

(

Acc: NRC312 Rubric (s): 293008K1.34 Correct Answer: 1

, Comp # 3533

Reference:

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

42. Natural circulation is inherent in a boiling water reactor (BWR). Which one of the following statements best describes natural circulation after a loss of offsite power?

1.

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

2.

Two-phase flow in the separators allows steam to be removed and liquid to return to the downcomer region.

3.

Relief and safety valves provide a heat sink for decay heat. In spite of leakage, cor. trol rod drives

{

are adequate to maintain inventory.

j 4.

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

i 9/88 l

NRC Exam - Form 6470101 Acc: NRC148 Rubric (s): 293009K1.17 Ccrrect Answer: 2 Comp # 3548 R:ference: Nuclear Power Plant Thermal Sciences, Reactor IIeat Generation, Reed Robert Burn, Chapter 10, p.10 - 6.

43. "The fuel bundle power that would cause the onset of transition boiling at some point in the fuel bundic"is the best 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 Correct Answer: 3 Comp # 3510

Reference:

Georgia Power Nuclear Training Manual; Training Lesson Plan Cycle Efficiency and the Real 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?

1.

If the feedwater flow rate used in the heat balance calculation was lower than the actual feedwater flow rate, then the ac"-

tower is higher than the currently calculated power.

2.

If the reactor recircuk.

i 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 the actual power is higher than the currently calculated power.

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 currently calculated power.

Acc: NRC26 Rubric (s): 2930091.10 Correct Answer: 4 Comp # 4040 R:ference: Ilrunswick Steam Electric Plant, IIcat Transfer, ch. 9, p.10.

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

l 1.

Linear heat generation rate (LIIGR) 2.

Total peaking factor 3.

Maximum thermal power 4.

Average planar linear heat generation rate (APLIIGR) 9/88 l

NRC Exan - Form 6470101 Acc: NRC49 Rubric (s): 2930051.05 C:rrect Answer: 2 Comp # 3968

Reference:

Brunswick, Steam Electric Plant, IIcat Transfer, ch. 6, p. 70.

I

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

)

1. The outlet of the high pressure turbine

2. The outlet of the moisture separators /rcheaters

3. 'Ihe inlet of the high pressure turbine

4. The outlet of the low pressure turbine Acc: NRC128 Rubric (s): 293006K1.05 Cctr:ct Answer: 3 Comp # 3703

Reference:

General Electric Operator Training Services. BWR Academic Se:its, IIcat Transfer and Muid How RWO, Sept. 85, Chapter 6, pp. 6-56a 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

3. Water hammer 4.

Pipe whip Acc: NRC185 Rubric (s): 293006K1.08 Corrcct Arawer: 3 Comp # 4112

Reference:

General Electric BWR Academics Series, IIcat Transfer and Muid Row,1985, pp. 6-96.

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

1.

Pump head is directly proportional to speed 2.

Power varies as the square of the speed i

1 3.

Pump head varies as the square of the speed l

4.

Capacity varies as the cube of the speed l

. 9/88

e, NRC Exam - Form 6470101 Acc: NRC03 Rubric (s): 2930071.06 C:rrect Answer: 4 Comp # 3928 Ref;rence: Westinghouse Thermal Hydraulic Principle and Applications, ch. 5, pp. 20 - 21.

QUESTION 49 REFERS TO TIIE FOLLOWING INFORMATION:

Given the following information:

- heat-transfer rate (Bta/hr)

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

Ah - enthalpy difference (Btu /lb)

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

Cp - specific Nat at constant pressure (B.u/lb *F) h - enthalpy of fluid (Btu /lb)

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

1.

- $(Ah) 2.

- hA( AT) 3.

- ACp(AT) 4.

Q - UA( AT)

Acc: NRC158 Rubric (s): 293004K1.13 Correct Answer: 4 Comp # 3525

Reference:

Brunswick Steam Electric Plant, IIeat Transfer, Chapter 8, page 8-45,

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

1.

Increase in condenser temperature 2.

Increase in the amount of noncondensable gas in the condenser 3.

Decrease in main turbine efficiency 4.

Increase in condensate subcooling 4 9/88

NRC Excm - Form 6470201 Acc: NRC80 Rubric (s): 291001K1.12 C:rrect Answer: 1 Comp # 3966 R:ference: NMP-2 BWR Academics, Heat Transfer and Fluid Flow, 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.

2.

the loss coefficient for a full open globe 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 Cctreet Answer: 4

- Comp # 3956

Reference:

General Electric BWR Academics Series Heat Transfer and Huid 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 Corr:ct Answer: 1 Comp # 3618

Reference:

NMP-2 EWR Academics, Heat Transfer and Huid How, 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 positive suction head?

l 1.

Loss of feedwater heating while at 80% power 2.

Increase in reactor coolant temperature from 100*F to 200*F during a reactor startup 3.

Decrease in reactor pressure during a normal reactor shutdown 4.

Decrease in reactor water level from the normallevel to just below the low-level alarm level l

l l 9/88

NRC Exam - Form 6470201 Acc: NRC92 Rubric (s): 291004K1.12 C:rrect Answer: 3 Comp # 3718 Ref rence: NMP-2 BWR Academics, Heat Transfer and Fluid Flow, T. Meadows, February 1985, p. 6-109.

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: NRCIS Rubric (s): 291002K1.15 Correct Answer: 1 Comp # 3938 R:f:ren;e: NRC Systems Manual BWRs, BWR/6 Design, Vol. I, Chapter 3, pp. 3.112 and 3.1-13. Mark's Standard llandbook for Mechanical Eugineers, Eighth Edition, p.1613.

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.

4.

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

Acc: NRC3%

Rubric (s): 291005K1.08 Correct Answer: 1 Rt ference: General Electric BWR Academics Series 1985, Electrical Science, AC Genciators and Motors.

6.

Generator excitation controls the megavar loading and power factor of generators operating l

synchronized 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 4.

Negative megavars and a lagging power factor l 9/88 1

l

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

, C:rrect 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:

1.

negating the reverse power protection on the lagging 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: NRC414 Rubric (s): 291002K1.09 Cctreet Answer: 3

Reference:

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

8. Reactor feedwater flow and vessellevel 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: NRC104 Rubric (s): 291006K1.01 Correct Answer: 2 Comp # 3916

Reference:

NRC Systems Manual BWRs, BWR/6 Design, Vol. 2, Chapter 10, p.10.4-14.

9.

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 ti.e war side to ensure that the cooldown rate does not exceed design limits.

Acc: NRC229 Rubric (s): 291006Kl.18 Correct Answer: 1 Comp # 3912

Reference:

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

10. 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.

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 Exam - Form 6470201 Acc: NRC96 Rubric (s): 291005K1.05 C:rrect Answer: 3 Comp # 3655 R;ftrence: NMP-2 BWR Academics, Heat Transfer and Fluid Flow, T. Meadows, February 1985, p. 6-108.

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 Cctreet Answer: 2 Comp # 3702

Reference:

NMP 2 BWR Academics, IIeat Transfer and Fluid Flow, T. Meadows, February 1985, p. 6-108.

12. 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 motor current.

Acc: NRC394 Rubric (s): 291003K1.06 Correct Answer: 4 Rsference: NNeco Training Dept. Unit No.1, Lesson Plan,1338, Emergency Diesel Generator, p.13.

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

1.

trips the diesel in the event 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. 9/88

NRC Exam - Form 6470201 Acc: NRC83 Rubric (s): 291002K1.01 Cctrect Answer: 1 Comp # 3935 R:ference: NMP-2 BWR Academics, Heat Transfer and Fluid Flow, T. Meadows, February 1985, pp. 6-67 and 6-70.

14. 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 orifice.

Acc: NRC373 Rubric (s): 291002K1.07 Corr:ct Answer: 3

Reference:

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

15. Which of the following parameters determines the maximum lesel that can be indicated by a reactor water-level instrument?

1.

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

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 9 9/88

i.

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

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

OUESTION 16 REFERS TO THE FOLLOWING DIAGRAM:

High Drywell Pressure a-_.,____,

Low Reactor l

Water Level i

r l

I I

i l

o l

Push Button g

Roset I

O I

I l

Seal-in I

[ Re, lay,_j me Delay

_ _ _.j pen

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

1.

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

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.

\\

e= 9/88

NRC Exam - Fcrm 6470201 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.

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

1.

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

2.

is controlled by complying with core thermal limits.

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

4.

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

Acc: NRC372 Rubric (s): 291002K1.07 Correct Answer: 1 R-Arence: 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:

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: NRC401 Rubric (s): 291001K1.01 Correct Answer: 2

, R:f:rence: River Bend, Licensed Operator Training Manual,1987, Main Steam, pp. 7--4.

19. 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 velve returns to the lifting set point, a combination of cir i

and steam pressure above the valve disk closes the valve.

2.

As reactor pressure increases to the safety set point, the pressure overcomes spring tension on the I

valve operator, causing the valve to open.

3.

As the disk oa 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 airoperated piston.

l

[

l l

7-9/88 t

a NRC Ex:m - Form 6470201 Acc: NRC406 Rubric (s): 291008K1.05

, Ccrrect Answer: 2

Reference:

Commonwealth Edison Company, Power Plant Electrical 7undamentals Book 5,1979, Section'4,

[

P.' 68.

i

'20. Thermal overload devices are used to protect circuits in nominal overload conditions. Which of the following d(6nes a thermal overload device?

1.

A balauced 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, everheats and actuates a circuit-

' interrupting device.

3. A temperature monitor that senses the ternperature 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 Cerrut Answer: 2 Comp # 4029 Referrace: 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 deminerahzer to detect silicate.

2.

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

3. sampling the intes 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 Correct Answer: 1 Comp # 3960 f

Reference:

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

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

1.

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

2.

temperature compensation is not required to obtain accurate flow rates because oater is an 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.

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

. 9/88

NRC Enm - F:rm 6470201 Acc: NRC109 Rubric (s): 292002K1.08 Correct Answer: 1

, Comp # 4005 Refer;nce: General Physics Corp., Academic Program for Nucler Power Plant Personnel, Volume II, Physics, Chapter 4, p. 4 - 54.

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

1.

supercritical 2.

critical 3.

subcritical 4.

prompt critical Acc: NRC254 Rubric (s): 292005K1.04 Cctreet Answer: 4 Comp # 3613

Reference:

General Electric BWR Academics Series Reactor Theory,1984, p. 5-25,

24. The "reverse power effect" or "reverse reactivity effect" occasionally observed when a shallow control 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.

4.

large local power increase being offset by a void related power decrease.

Acc: NRC76 Rubric (s): 292006K1.22 Corrret Answer: 2 Comp # 3474

Reference:

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

25. In regard to xenon 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 first 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , while samarium concentration decreases.

2.

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

l 1

Xenon concentration increases, while samarium concentration remains at equilibrium.

4.

Xenon concentration decreases, while samarium concentration remains at equilibrium.

l l

l 9/88 t

NRC Ext.m - Form 6470201 Acc: NRC305 Rubric (s): 292008K1.20 Correct Answer: 2 Comp # 4010 Refer:nce: General Electric BWR Academics Series, Reactor Theory,1984, pp. 4-5 to 5-10.

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

1.

Increasing fuel temperature implies more heat transfer to the coolant. 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 increashg steam generation. The 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. The increased steam generation raises reactor pressure and moderator temperature, offsetting the decreased voids, 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 j

Comp # 3531 R:ference: Introduction to Nuclear Reactor Operations, Reactor Kinetics, Reed Robert Burn, p 4 - 4.

27. After initial criticality, a reactor is leveled off. The source range channels are repositioned so that the count rate is 100 cps. Sumcient 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 2.

4 minutes 3.

9.21 minutes 4.

15.82 minutes Acc: NRC145 Rubric (s): 292004K1.01 Correct Answer: 2 Comp # 3594

Reference:

Brunswick Steam Electric Plant, Reactor Theory, Chapter 14, p.164.

28. "The change in reactivity produced by a unit change in reactor coolant temperature" defines which of the following reactivity coemcier,ts?

1.

Void 2.

Moderator 3.

Power 4.

Doppler 9/88

NRC Exam - F:rm 6470201 i

Acc: NRC175 Rubric (s): 292008K1.04 3

f Correct Answer: 2 Comp # 4066 1

Ref:rence: General Electric BWR Academics Series Rector Theory 1984, pp. 7-6

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

1.

Control rod worth 2.

Source range iaitial count rate 3.

Fuel temperature 4.

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

Comp # 3977

Reference:

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

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

l

1. To minimize the potential of moving high-worth control rods

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 l

Correct Answer: 1 Comp # 4027 t

Ref;rence: General Electric BWR Academics Series Reactor Theory,1984, pp. 3-5 to 3-12.

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

1.

Neutron source, moderator, and fissionable material 2.

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

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

Fissionable material, moderator, and K,, greater than one 9/88

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

- Cctrect Answer: 4 Comp # 4025 R;ference: General Electric BWR Academics Series, Reactor Theory,1984, pp.1 - 38.

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

1.

AK 2.

K,,

3.

K,,-1 r

4.

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

Reference:

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

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,, t proaches 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 becoming slightly supercritical, due to a "prompt jump", and then returo to a suberiticallevel.

4.

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

L Acc: NRC42 Rubrir(s): 2920081.19 Correct Answer: 2 Comp # 3933

Reference:

Brunswick, Ster.m Electric Plant, Reactor Deory, ch.14, p.190.

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.

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

2.

Vold fraction increases.

3. Void fraction decreases.

4.

Void fraction remains the same.

I

- 9/88

NRC Exam - Form 6470201 Acc: NRC56 Rubric (s): 2920011.02 Correct Answer: 3 Comp # 4001, Ref:rence: General Electric BWR Academics Series, Rector Theory,1984, pp. 3 - 21.

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.

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

4.

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

Acc: NRC114 Rubric (s): 292006K1.11 Ccrrect Answer: 1 Comp # 3990

Reference:

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

36. A power reactor has been operating at 50% power for 4 days. Power is then increased to 100% over a 1-hour period. Which of the following expresses the time range during which the minimum concentration of xenon is expected to occur after the power increase?

1.

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

10 - 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.

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

19 - 21 hours2.430556e-4 days 0.00583 hours 3.472222e-5 weeks 7.9905e-6 months Acc: NRC158 Rubric (s): 293004K1.13 Correct Answer: 4 Comp # 3525

Reference:

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

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

1.

Increase in condenser temperature 2.

Increase in the amount of noncondensable gas in the condenser 3.

Decrease in main turbine emeiency 4.

Increase in condensate subcooling

. 9/88

NRC Exam - Form 6470201 Acc: NRC03 Rubric (s): 2930071.06 Correct Antwer: 4 Comp # 3928 2

R:fsr:nce: Westinghouse Thermal Ilydraulic Principle and Applications, ch. 5, pp. 20 - 21.

QUESTION 38 REFERS TO TIIE FOLLOWING INFORMATION:

Given the following information:

- heat-transfer rate (Btu /hr)

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

Ah - enthalpy difference (Blu/lb)

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

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

38. Which one of the following formulas is most representative of the heat-transfer rate across the tu'xs of a heat exchanger?

1.

- $(Ah) 2.

- hA(AT) 3.

- sCp(AT) 4.

- UA(AT)

Acc: NRC185 Rubiic(s): 293006K1.08 Ccrrect Answer: 3 Comp # 4112 R:ference: General Electric BWR Academics Series, IIcat Transfer and Fluid Flow,1985, pp. 6-96.

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

1.

Pump head is directly proportional to speed 2.

Power varies as the square of the speed 3.

Pump head varies as the square ot' the speed 4.

Capacity varies as the cube of the speed

. 9/88

NRC Exam - Form 6470201 Acc: NRC128 Rubric (s): 293006K1.05 C6rrect Answer: 3 Comp # 3703

Reference:

General Electric Operator Training Drvices. BWR Academic Series, IIcat Transfer and Fluid Flow RWO, Sept. 85, Chapter 6, pp. t. 56a 59a

40. Given a sudden stop in a fluid flow in a piping s3 tem due to rapid closure of an outlet valve, which one of the following terms best de:cribes the press e change in the system?

1.

Cavitation 2.

Shutoff head 3.

Water hammer 4.

Pipe whip Acc: NRC49 Rubric (s): 2930051.05 Correct Answer: 2

. Comp # 3958 Refsrence: Brunswick, Steam Electric Plant, IIent Transfer, ch. 6, p. 70.

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

1.

The outlet of the high pressure turbine

2. The outlet of the moisture separators / reheaters

3. The inlet of the high pressure turbine 4.

The outlet of the low pressure turbine Acc: NRC26 Rubric (s): 2930091.10 1

Correct Answer: 4 Comp # 4040

Reference:

Brunswick Steam Electric Plant, IIcat Transfer, ch. 9, p. 70.

f

42. Which of the following thermallimits protects the fuel from reaching 2200*F following a loss-of coolant accident (LOCA)7 1.

Linear heat generation rate (LIIGR) 2.

Total peaking factor 3.

Maximum thermal power j

4.

Average planar linear heat generation rate (APLIIGR)

{

l i 9/88

~

NRC Excm - Form 6470201 Acc: NRC209 Rubric (s): 293007K1.13 Cctreet Answer: 3

' Comp # 3510 Referencei Georgia Power Nuclear Training Manual; Training Lesson Plan Cycle Efficiency and the Real Cycle,1985, pp.11 - 15.

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

1.

If the feedwr.ter flow rate used in the heat balance calculation was lower than the actual feed 7:ater flow rate, then the actual power is higher than the currently calculated power.

t 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 herit balance calculation was lower than the actual steam flow, then the actual power is higher than the currently calculated power.

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 currently calculated power.

Acc: NRC148 Rubric (s): 293009K1.17 Cerr:ct Answer: 2 Ccmp # 3548

Reference:

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

44. "The fuel bundle power that would cause the onset of transition boillag at some po:nt in the fuel bundle" is the best 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: NRC312 Rubric (s): 293008K1.34 Correct Answer: 1 Comp # 3533

Reference:

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

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

)

2. Two phase flow in the separators allows steam to be removed and liquid to return to the downcomer region.

3.

Relief and safety vrdves provide a heat sink for decay heat. In spite of leakage, control rod drives are adegunte to maintain inventory.

4.

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

the core.

( 9/88

{

NRC Exan - Form 6470201 Acc: NRC09 Rubric (s): 2930081.07

. Correct Answer: 1 Comp # 4015 R:ference: Westinghouse Thermal Hydraulic Principles and Applications, ch. 3, p. 59.

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

1.

Subcooled nucleate boiling 2.

Saturated convection 3.

Subcooled convection 4.

Saturated nucleate boiling Acc: NRC06 Rubric (s): 2930081.23 Correct Answer: 4 Comp # 3645

Reference:

Wes.tinghouse Thermal Dynamic Principles and Applications, ch. 7, pp.13 - 14, Steam Tables Motiler Diagram.

47. Which of the following values most accurately represents the quality of steam leaving a cyclone separator at 985 psig and 1183 Btu /lb7 1.

95 %

2.

96%

3.

97 %

4.

99 %

Acc: NRC221 Rubric (s): 293003K1.23 l

Ccrrect Answer: 4 l

Comp # 3939 l

Reference:

Steam Tables.

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

l 1.

420*F l

2.

425'F 3.

430'F 4.

435'F l 9/88

.c NRC Exam - Form 6470201

.a Acc: NRC169 Rubric (s): 293007K1.01 C:rrect Answer: 4 Comp # 3468

Reference:

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

49. Which of the following methods of heat 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: NRC162 Rubric (s): 293009K1.21 C:rrect Answer: 2 Comp # 3505

Reference:

IIcat Transfer and Fluid Flow, BWR Academics Series, General Electric, Chapter 9, page 9-15a

50. Which of the following limits or conditions is avoided 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.

Fuel cladding cracking due to high stress 4

9

. 9/88

u) \\

-.v:.

A 4

Docket No.

50-331 Mr. William C. Rothert Iowa Electric and Power Company P. O.

Box 351 Cedar Rapids, Iowa 52406

Dear Mr. Rothert,

on September 21, 1988, the NRC administered a Generic Funda-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 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 t

decides to substitute the results of this examination for the-first section of the site specific 4 examination, he or she must request a waiver of this section of the examination on his or i

her NRC form 398.

If no waiver is requested the candidate will l

be required to take the entire site specific examination.

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

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 4 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 CFR 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-inees are exempt from disclosure, therefore enclosures (5) and (C) will not be placed in NRC's Public Document Room.

0

)

In order to better evaluate this pilot examination and improve the design of our future examinations, we have included with this letter voluntary Feedback 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 time to return them with your evaluations.

This request was approved by the office of Manage %ent 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) 492-1046.

Sincerely, Kentieth E.

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

Enclosures:

1.

Examination Form "A" with answers and references Examination Form "B" ' ith answers and references 2.

W 3.

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

4.

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

l S.

Examination Results Summary for Duane Arnold.

6.

Copies of Candidate's individual answer sheets.

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l 1

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o 0

Docket No.

50-341 Mr. Ralph Sylvia Senior Vice President i

Detroit Edison Company 6400 North bixie Highway l

Newp*,rt, Michigan 48166 l

Dear Mr. Syltia,

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

"loaed with this letter are the grading and answer sheets for examinnvions.

You are requested to forward these results

.ha examinees along with copies of their answer sheets.

A

.x in the column labeled Final Grade indicates a passing grade

.e cor this examination.

h T: a car,uidaae for an operator or a senior operator license voc2J.cs to uubrtitute the results of this er:.mination for the farsa section of ths site specific examination, he or she must

'equest a waiver of this section of the examination on his or hwr WRC form 398.

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

For candidated requesting a waiver, the results of the pilot examin-atima wi'.1 be totaled with the other sections of the site speci-fic 1xamina'. ion to obtain an overall examination score.

If an applicent "or either an RO or SRO license takes the current four section examination, the pilot examination resul:s will count for 254 of the total, and if the candidate takes the new three stetian examination it will count for 25 % for the overall operator examination score or 24 4 for the overall senior oper-atof examination score.

The passing grade for an NRC adminis-tered licensing examination is 80%, includina 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-I inees are exempt from disclosure, therefore enclosures (5) and (6) will not be placed in NRC's Public Document Room.

4 In order to better esaluate this pilot examination and improve the design of our future examinations, we have included with this letter voluntary Feedback 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 time to return them with your evaluations.

This request was approved by the Office of Management and Budget under clearanca 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 Executivo Office Building, Washington DC 20503.

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

Sincerely, Kenneth E. Perkins Jr., Chief Operator Licensing Branch Division of Licensee 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 Forms concerning Pilot Examination for examinees.

4.

Copies of voluntary Examination Feedback Forms concerning Pilot Examination for trainers.

5, Examination Results Summary for Termi 2.

6.

Copies of candidate's individual answer sheets.

i

i e.

i

so

.o I

d 1

Docket No.

50-373 i

Mr. Ray H. Raguse t

Commonwealth Edison Production Training Center j

l Rural Route 92. Box 120 Willaington, Illinois 60481 1

~

Dear Mr. Raguse,

On September 21, 1988, the NRC administered a Generic Funda-1 mentals pilot exar.ination.to employees of your facility.

l 1

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

You are requested to forward these results f

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.

d l

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

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 i

her NRC form 398.

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

For candidates requesting a waiver, the results of the pilot examin-I t

1 ation will be totaled with the other sections of the site speci-I fic examination to obtain an overall examination score.

If an 4

applicant for either an RO or PRO license takes the current four l

section examination, the pilot examination results will count i

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 oper-t ator examination score.

The passing grade for an NRC adminis-l tered licensing examination is 804, includina the fundamentals

[

section.

Passing Grade for the Fundamentals section is 70%.

)

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

[

in the Public Documents Room.

The results for individual exam-I inees are exempt from disclosure,,therefore enclosures (5) and I

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

l I

l J

4 In order to better avutuate this pilot examination and improve the design of our future examinations, we have included with this letter voluntary Feedback 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 -hat you take the time to return them with your evaluations.

This 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 Budget, Reports Manage-ment, Room 3208, New Executive Office Building, Washinicon DC 20503.

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

Sincerely, Kenneth E. Perkins Jr., Chief Operator Licensing Dranch Division of Licensee Performance and Quality Evaluation, NRR, NRC i'

Enclosures:

1.

Examination Form "A" with answers and references i

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 f

concerning Pilot Examination for trainers.

5.

Examination Results Summary for Lasalle County.

6.

Copic.2 of Candidate's individual answer sheeta.

l l

l y

m-

0 O.

Docket No.

50-263 Mr. Douglas D. Antony Monticello Training Center Northern States Power Company 2100 West River Street Monticello, MN 55362

Dear Mr. Antony,

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

Enclosed with this letter are thi rading and answer sheets for these examinations.

You are requested to 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 licenre decides to substitute the results of this examination for the first section of the sito 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 will be required to take the entire site specific examination.

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

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 oper-i ator examination score.

The passing grade for an NRC adminis-tared licensing examination is 80%, includ3ng the fundamentals section.

Passing Grade for the Fundamentals Section is 70%.

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

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

l r

l

s In order to better evaluate this pilot examination and improve the design of our future examinations, we have included with this letter voluntary Feedback 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 time to return them with your evaluations.

This request was approv: '. by the Of fice 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 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) 492-1046.

Sincerely, Kenneth E.

Perkins Jr., Chief Operator Licensing Branch Division of Licensee 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 Forms concerning Pilot Examination for examinees.

4.

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

5.

Examination Results Summary for Monticello.

6.

Copies of Candidate's individual answer sheets.

f c

Docket No.

50-440 Mr. Michael P.

Lazar The Cleveland Electric Illuminating Company P. O. Box 97 Perry, Ohio 44081

Dear Mr. Lazar,

on September 21, 1988, the NRC administered a Generic Funda-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 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 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 caniidate will be required to take the entire site specific examination.

For candidates requesting a waiver, the results of the pilot examin-ation will be totaled with the other sections of the site speci-fic examination to obtkin an overall examination score.

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 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 CFR 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 exim-inees are exempt from disclosure, therefore enclosures (5) and (6) will not be placed in NRC's Public Document Room.

L

v..

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

Because of the pilot 1

nature of this examination, we request that you take the time to I

return them with your evaluations.

I This 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 l

directed to the office of Management and Budget, Reports Manage-ment, Room 3208, New Executive Office Building, Washington DC l

20503.

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

l Sincerely,

[

l Kenneth E.

Perkins Jr., Chief Operator Licensing Branch Division of Licensee Performance j

l and Quality Evaluation, NRR, NRC I

l Enclosures I

1.

Examination Form "A" with answers and references 2.

Examination Form "B" with answers and references j

3.

Copies of Voluntary Examination Feedback Forms I

concerning Pilot Examination for examinees.

4.

Copies of Voluntary Examination Feedback Forms i

concerning Pilot Examination for trainers.

l 5.

Examination Results Summary for Perry.

6.

Copies of Candidate's individual answer sheets.

i 1

i l

l l

Docket No.

50-254 Mr. Jeffroy Neal Training Supervisor Quad Cities Nuclear Power Station Commonwealth Edison 22710 206 Avenus Norta:

Cordova, Illinois 61242

Dear Mr. Neal,

On September 21, 1988, the NRC administered a Generic Funda-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 to the examinees along with copies of their answer sheets.

A "OR" 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 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 will be required to take the entire site specific examination.

For candidates requesting a waiver, the results of the pilot examin-ation will be totaled with the other sections of the site speci-fic examination to obtain an ovsrall examination score.

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 oper-ator examination score.

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

Passing Grade for the Fundamentals Section is 70%.

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

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

In order to better evaluate this pilot examination and improve the design of our future examinations, we have included with this letter voluntary Feedback 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 time to return them with your evaluations.

This 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 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) 492-1046.

Sincerely, Kenneth E.

Perkins Sr., Chief Operator Licensing Branch Division of Licensee Performance and Quality Evaluation, NRR, NRC l

Enclosures:

1.

Examination Form "A" with answers and references 2.

Examination Form "B" with answers and references 3.

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

l 4.

Copies of Voluntary Examination Feedback Forms I

concerning Pilot Examination for trainers.

5.

Examination Results Sunmary for Quad Cities.

6.

Copies of Candidate's individual answer sheets.

l l

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l l

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[

WILVIARY IWDAMENIAIS EXAMD& TION FEEDBACK QUESTIONNAIRE Pilot-Test Participants' Fom Nana Student ID Fom of Exam Ccapleted (Circle One)

A B

DUlHETICNS

'Ihe Furdamentals Exam contains 22 questions related to Corponents,14 related to Reactor 'Iheory, and 14 to 'Ihermodynamics. On this famihack form, you are asked to evaluate the examination questions in each of these three areas ard to answer scas general questions about the examination.

It should take you about 30 to 45 minutes to ocmplete the famihack form. Please refer to the copy of the Nndamentals Exam included in your packet of test materials to ocuplete the famihack form. Your specific f

ck is greatly appzweiated.

Please return this form, along with the Background Information Form, to the address provided on page 7.

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

l l

l Question l Single Item l

Familiar With lVery very 1 Clearly l correct Number l

Content?

l Easy Average Difficult l Stated?

lPesponse?

I I

I I If No, II I

I l Yes/No l Peason l1 2 3 4 5 6 7 l Yes/No l Yes/No l

I I

Yes h l @ b, c l 1 5 h7 l h No Yesh 1

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

He was not familiar widt the test content (No) becauss it was not crwered 4

in the training program (Peasen a).

He rated the item difficult (6).

'Ihe question is clearly statai (Yes).

'Ihe question does not have a single correct respense (No).

4 Explamtions of each of these categories are provided on the following page. Continued Next Page i

4 Fa=414me with Ctmtant? Answer Yes if you Were familiar with the question content.

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

1 a) it was not coverud in your training program.

b) question content is not relevant for your facility, c) you simply did not recall the information at the time you took the exam.

O M ion Difficulty. Use the following definitions to rate the difficulty of each question on a 1 through 7 scales very Easy = A question that can be answered correctly by someone who has Det ocupleted the fundamentals portion of the training program.

l t

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

Very Difficult = A question that cannot be answered correctly by smoone who i

has empleted the temantals portion of the training program.

O M ion claarly Statad? If an item is clearly stated, circle Yes. If it is unclear or difficult to understand, circle No.

Simle cce. cit. Response? If there is gas and only one correct answer, circle l

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

l The form for your individual question evaluations begins on the next page, I

i followed by the general questions about the examination.

6 I

i f

i I

2-Continued Next Page l

.m-+4Y*-w

' w wwwtw wwe +

_emwee+-,,-e-,,e e

sw--

I I

I omstion Isingle Item l

Familiar With lVery Very l Clearly

[ Correct Number l

Content?

l Easy Average Difficult l Stated?

l Response?

I l

l l

l If No, ll l

l l

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

I I

l I

l l

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

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

Yes/No l Yes/No l

I I

I 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 Yes/No I

l l

I 5

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

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

Yes/No l Yes/No l

I I

7 l Yes/No 1 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

l l

l 1

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

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

I l

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

l L

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

I I

i 1

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

Yes/No l Yes/No l

l l

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

Yes/No l Yes/No 18 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 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 tes/No l

I I

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

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

Yes/No l Yes/No i

I I

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

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

I I

I I o:ntinued Not Pegs

Evaluations of D etination Ouestions (cont'd) l l

l Question l Single Item l

Familiar With lVery Very l

Clearly l Correct Number l

Content?

l Easy Average Difficult l Stated?

lResperse?

I l

l l

l l If No, Il l

l l

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

I l

1 l

I I

l l

1 l

l l

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 l

l l

l 1

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

Yes/No l Yes/No 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

31 l Yes/Ns 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 l

I l

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/ho l

l l

I 1

35 l Yes/No l a, b, c l 1 2 3 4 0 6 7 l

Yes/No l Yes/No 36 l Yes/No l a, ', c l 1 2 3 4 5 5 7 l Yes/No l Yer/No l

l I

I 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 I

I l

I 1

39 l Yes/No l a, b, c l 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 l

I I

I l

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

I i

I I

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

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

I I

l l

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

Yes/No l Yes/No 46 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

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

Yes/No l Yes/No i

I I

49 l Yes/No l a, b, e l 1 2 3 4 5 6 7 l Yes/No l Yes/N(.,

50 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 Cbntinued Next Page

GDIERAL OUESTICitS ABCUT NE FtHDfMNTAIS EXAMINATION In this section, we ask you to answer specific questions about each of the three sections in the exam (Cwwsts, Reactor teory, and nermo-dynamics) and scas general questions about the exam.

For each statement appearing belcw, please indicate your response by circling Yes or No.

If you Want to provide coumants about your respcrees to these items, please write them in the space below each item. You can also provide additional camments about the exam in the last section.

O:rioonents Questions (Items 1 to 221 Yes No 1.

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

Yes No 2.

Do the 22 exam questions ocmprehensively sanple Cwwmts material presented in your training program?

Reactor teory Ouestions fItems 23 to 36)

Yes No 3.

Do the 14 exam questions represent a good measure of basic Reactor Weory knowle&e?

J Yes No 4.

Do the 14 exam questions emprehensively sanple Reacter teory material presented in your training program?

herrah'namics Questions fItama 37 to 50) l Yes No 5.

[b the 14 exam questions represent a good measure of basic

%emodynamics knowledge?

Yes No 6.

Do the 14 exam questions ocmprehensively emrple termodynamico material presented in your training program?

t Yes No 7.

Is it reasonable to expect an individual with satisfactory knowla.ke of the subject areas to cxmplete the ntndamentals J

Exam in two hours or less?

! 0:ntinued Next Page

General Mims @_t the M-*21m h (ocnt'd)

Yes No 8.

Should more iterns be added to this exam to ensure ocaprehensive coverage?

H I

Yes No 9.

Can these knowledge areas be ocaprehensively tested with fewer items?

l Yes No

10. Do you believe that it is manavy for smoons to have ocupleted all or part of the training pregram 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 program need to attsty to obtain a score of 70% or higher en the exam?

Yes 1%

12. Would you teommani that a passing score en this exam be required of all non-licensed operators prior to reo2iving an NRC license?

Yes No 2*.

In general, is this exam too difficult?

(Diffioult is detined as containing many itans that cannot be answered correctly by training program.) pleted the fundamentals portion of the scajems who has ocu Yes No

14. In general, is this exam too easy?

(Easy is defined as oc.y taining many itens that can be answered correctly by scamens who has D3 ocupleted the furdamentals portion of the training p % =m.)

Yes No 15.

Is the paroentage of itaan for the three sections appropriate for this exam (i.e., C+sts, 444; Reactor Theory, 28%; and Thermodynamics, 28%)?

Yes No

16. Does this exam measure knowledge required to ama== fully ocyplete t;wn Cwists, Reactor Theory, and Wwunics sections of the operator training program? Continued Next Page

Yes 2

17. Was the material coverud in this exam presented early in your training program?

Yes No 18.

In general, do scorse on this exam represent good indicators of how well an iMividual viu perform on the job as a licensed operator?

Yes No 19.

Do you feel that your exam score representa your knowledge about the three areas?

General Cb mants If you have additional ocanants that you would like to make about the Fundamentals Damination, please provide them below.

P I

I I

l hv* you for your input. Please return this questionnaire, along with the i

Backgrouni Information Form, to t

I.an Wiens

(

U.S. NRC L

Mail Stop Ch7N 10-D 18 Washingtcn, DC 20555 1

i i

e PIIUr-TEST PARTICIPANIS' BAC3GOUND INitFMATICH FCiH Name Student ID Fom of Emm Ccmpleted (circle one) A B

on this for'm, we ask you to prcuide sme background infortation about I

yourself.

Please note that your participation is strictly voluntary. The information you pr: vide will be used to detemine whether or not scores on the R:ndamentals Examination serve as useful indicators of operator training program experience and/or backgrcund.

This request was approved by the office of Management and B.dget urder clearance number 3150-0090. Clearance number 3150-0090 expires on Nov 30, 1988. Ocenents on burden and duplication may be directed to the Office of Management and !!udget, Reports Management, Rocen 3208, New Executive office Bldg., Washington, D.C. 20503.

If you have any questions about this fom, please contact Mr. Ian Wiens at NRC Headquarters (phone 301-492-3171). Please mail this fom, along with the Examination Fa=*ack Questionnaire, to the address provided on Page 4.

The following questions ask for information about your education, train-ing, and job experience. Please read each question and answer by ciroling the one response that describes you best or filling in the blanks where indicated.

ECUCATICU 1.

khat is your highest level of education?

4 a.

High School GED l

b.

High School graduate t

c.

Attended Vocational-Technical school I

d.

Graduated from a Vocaticnal-Technical school e.

Scne college course work f.

Graduate fran a two-year college program r

g.

Graduate fran a four-year college program i

h.

Sme graduate ocurse work i

)

1.

Ctmpleted a graduate program, i

2.

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

a.

Nuclear Engineering b.

Other Engineering (please specify) c.

Fhysical Sciences (plesse specify) f j

d.

Mathe:ratics and Ccrputer Sciences o.

Other (please specify) i i

i i

I i

. Chntinued Next Page

(

I i

3.

If you ccepleted college, please inlicate then you graduated.

Month Year 4.

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

(Do not include the licensed operator training prrgram shen answerirg this question.)

a.

Yes If yes, indicate the nurber of courses b.

lio MILITARY TPAI161C EXPmIDICE 5.

Please indicate if you have served in a bran:h of the U.S. military.

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

a.

b.

Arny c.

Air Fcree d.

Ihrine corps e.

Navy f.

Coast Guard 6.

If ycu served in the Navy, did you kerk in the Nuclear Propulsion Program?

a.

Yes If yes, indicate how leny you served:

l Years ibntha b.

No 7.

If you cerved in the U.S Naw Nuclear PrTulsion Frvuam, please l

answer questions A and B below.

A.

Inilcate the highest position held in the nuclear propulsion

program, a.

herulsion Plant Watch Officer b.

Ergineerirg Watch Supervisor c.

Engina Rocza Supervisor d.

Reactor Cyerator e.

Chief, Reactor Watch f.

Ergineerirn Officer of Watch g.

Propulsion Plant Watch Supervisor h.

Other (please specify)

B.

Iniicate the tire period in thich Stu served in the position identified in Item A above.

Frtn lbnth Yea" To tbnth -

Year Continued Neat Page

a I

LICDTSED OPERATOR TPADTDG PPOGPAM EXPERIDICE 8.

Please answ.r questions A, B, C, ard D about the licensM operator trainirq prcgram.

A.

Are you currently enrolled in the licenscd operator prtgram?

a.

Yes b.

lio.

I have already cx2pletM the prtgram.

c.

No. I will soon begin the trainirq prcgram.

d.

No.

I do not plan to take this training prtgram.

B.

If you are currentiv enrr2Rg) in the licensed cperator ocurse, please specify how much of the program you have ocepleted to date.

weeks out of weeks for the total training program.

C.

If ycu have already octrleted the traininy prtgram, please irdicate the date that lui ccepletM it.

Month Year D.

If ycu clan to begin the trainira crocram, please indicate

% hen.

Ibnth Year 9.

Belev, please ansa r questiens about specific lioersed cperator trainiry courses that lui have ccrpleted.

A.

Ibve you ccupleted a cx:urse in Paactor Theor/?

a.

Yes P1mse inlicate the date ocepletedt lbnth _

Year b.

No B.

Have ycu ocrpletM a ccurse in Ccrponents?

a.

Yes Please iniicate the date ccepletMt Fbnth Year b.

No C.

Ibve ycu ccrpleted a ecurse in Therxd m:: Lies?

i a.

Yes Please iniicate the data ccepleted:

tbnth Yer b.

No Continued Next Page

t D.

If you plan to begin the training program, please irdicate when:

Month Year JOB EXPERIDiCE 10.

khat is your present job?

a.

lion-licensed / auxiliary /oqui;rait operator b.

Paactor cperator c.

Senior reactor operator d.

Shift technical advisor (STA) e.

Shitt supervisor f.

Other (please specify) 11.

Mcw long have you or did you work as a non-licensed / auxiliary /equignent operator?

a.

Ibnths Years b.

Does not apply, have never worked as a non-licensed / auxiliary /equisnent operator.

12.

Mcv long have you spent in your present job? Please ansa r this question even if it is the m as ermer #11 abwe.

Months Years 13.

khat is the total time ycu have worked in a ocx:nercial nuclear pcLur plant?

Months Years

'Ihank you for takiry the time to crrplete this fom. Please mail this, along with the Dcamimtion Feedback Questiennaire to:

Ian Wiens U.S. Imc Msil Stop CWm 10-D 18 Washington DC 20555 f

PIIDI-TEST PARTICIPANTS' BAC3GCUND INFCFMATICtf FORM Name Student ID Form of Exam Capleted (circle one) A B

On this ferm, we ask you to prwida some background information about yourself. Please note that your participation is strictly voluntary. The information you prwide will be used to determine whether or not scores on the Fundamentals Dca:dnation serve as useful indicators of operator training program experience an4/or backgrourd.

This request was apprwed by the Office of Management and Budget trcder clearance number 3150-0090. Clearance number 3150-0090 expires on Nw 30, 1988. Cements on burt$en and duplication may be directed to the Office of Management and Edget, Reports Ma% at, Roan 3208, New Executive offion Bldg., Washington, D.C. 20503.

If you have any questicns about this form, please cen*.act Mr. Ian Wiens at NRC Headquarters (phone 301-492-3171). Please mail this form, along with the Examinaticn Feedback Questionnaire, to the ailross prwided on Page 4.

The following questions ask for information about your education, train-ing, and job experience. Please read each question and answer by circlim the 4

one response that describes you best or filling in the blanks Mare indicated.

EDUCATICH

)

l 1.

Wat is your highest level of education?

I a.

High School GED b.

High School graduate c.

Atterded Vocational-Technical school d.

Gr.duated frta a Vocaticnal-Technical s. tool e.

Scne college course work l

i f.

Graduate frta a two-year college program g.

Graduate frt:an a four-year college prv.m h.

Scas graduate ocurse work i.

Oxpleted a graduate program.

l

~

j 2.

If you ocrpleted college (2-or 4-year program), please identify your l

major program.

j a.

Nuclear Engineering t

b.

Other Engineering (please specify) c.

m ysical Sciences (please specify) d.

Mathematics and Ccrputer Sciences e.

Other (please specify)

- Continued Next Page

o g

3.

If you ocupleted college, please indicate utan you graduated.

Month Year v

4.

Have you taken college ocurse(s) in ruclear energy? (Do not include the licensed operator training program when answering this question.)

a.

Yes If yes, iniicate the number of ocurses b.

No l

i t

MILITARY 'mAINING EXPERTm3 Please indicate if you have served in a branch of the U.S..:silitary.

5.

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

a.

b.

Army m

c.

Air Force d.

Marine Corps i

e.

Navy f.

Coast Guard

/l 6.

If you served in the Navy, did you work in the Nuclear Propulsion l

Program?

a.

Yes If yes, indicate how lcog you served:

f Years Months b.

No l

i 7.

If you served in the U.S Navy Nuclear Proculsicm PHuram, please

(

r answer questions A and B below.

A.

Indicate the hit $est position held in the nuclear propulsion l

pr @ mm.

a.

Prtpulsion Plant Wat& officer i

b.

Engineering Wat & Supervisor c.

Engine Ibcu Supervisor d.

Reactor Operator e.

Chief, Reactor Wate f.

Engineering officer of Wat&

{

g.

Propulsion Plant Wat e Supervisor i

h.

Other (please specify)

Indicate the time period in which you served in the position I

B.

identified in Item A above.

I Frant Month Year i

Tot Month Year i

t

' Continued Next Page t

l l

l

O IICDISED OPERATOR TRADTING PROGRAM EXPERIDiCE t

8.

Please answer questions A, B, C, and D about t?A licensed operator trainire pttgram.

A.

Are you currently enrolled in the licensed operator program?

I a.

Yes b.

No. I have already empleted the program.

c.

No. I will soon begin the training pregam.

d.

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

B.

If you are currently enrolled in the licensed operator course, please specify how axh of the program you have ocmgGeted to date.

weeks out of weeks for the total training program.

C.

If you have already acroleted the training program, please indicate the date that you ocupleted it.

Month Year D.

If you clan to bacin the trainira pIggne, pleasa indicate when.

Month Year 9.

Below, please answer questions about specific licensed operator training ocurs w that you have ocupleted.

A.

Have you ocepleted a ocurse in Reactor Theory?

a.

Yes Please indicata the date ocmpleted:

Month Year b.

No B.

Have you cxmpleted a course in Cm.Ents?

a.

Yes Please indicata the date ocupleted:

Month b.

No Year C.

Have ycu ocmpleted a ocurse in Thermodynamics?

a.

Yes Please indicate the date ocrpleted:

Manth Year b.

No

. Continued Next Fage

o a

l 0

4

- i D.

If you plan to begin the training program, please inlicate When:

Month Year I

i JOB EXPERIINCE (lk' 10.

What is your present job?

Ncn-license 4/ auxiliary /equignant cperator a.

b.

Reactor operator c.

Senior reactor operator d.

shift technical advisor (STA) i e.

shift supervisor f.

Other (please specify) 1 T

11.

How 1cmg have you or did you work as a non-license 4/ auxiliary /equipnent operator?

i a.

Months Years b.

Does not apply, have never worked as a 4

n.1n-license 4/ auxiliary /equipnent oprator.

4 12.

How long have you spent in your present jcb? Pieme answer this question even if it is the uame as answer $11 above.

t Months Years 1

13.

What is the total time you have worked in a ocssarcial naclear i

l j

power plant?

i 5

3:

Months Years l

i I

Thank you for taking the time to caplete this form. Ploem mail this, along with the Examination Feedback Questierrairs tot i

L Ian Wiens U.S. NRC f

Hail stop cWrw lo-D 2a l

Washington DC 20555

(

L I

I l.

t

~

o VOILWIARY P1]NDEENIAIS EXAMDETICH PIEDBACK QUESTICtORIRE Trainers' and Examiners' Fom I

Facility / Site Did you take the Funehmentals Examination? (Circle one)

Yes No If Yes, please answer followirq questions:

Student ID Exam Form (Circle one) A B

INS'IRICTICNS Ihe Fun 4mmentals Exam contains 22 questicris zulated to Caipors tta,14 related e

to Reactor 'Ibeory, and 14 to lharmodinamigg. On tnis faar*ack fom, you are asked to evaluate the examination questions in each of these three areas and to answet scans general questicos about the examination. It should take you scout 30 to 45 uinutes to exrplete the fam4hnck fom.

Please refer to the copy of the Fundamentals Exam included in your packet of test natuials to ocuplete the feedback foin. Your specific famihack is greatly appreciated.

Please return this form to the ediress provided on page 7.

t j

Please evaluate each of the exam questicos as shown in the exanple below. As a trainer or exaniner, we would like you to consider how relavant eat ques-tion is for non-licensed coerators tarticinatim in the e==_mter licensim trainim mimam.

1 l

l l

Ques *lon lsinglo Itam l

Fami)iar Wath 1Very very cleerly Icorrect i

Number l

Ocotant?

l Easy Average Difficult l Statal?

l Response?

I I

I 1

l 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

l I

i i

I i

i Yes @ I @ b, l

l1 2 3 4 5@7 lh h Yes@

[

1 In this exanpla, the trainer evaluated question rumber 1 ac follows:

i Non-2 toensel operators would not be familiar with the test content (No)

I because it is rxt. covazid in the tnining program (Reason a).

l j

'Ihe item is ratai as difficult (6)

The question is clearly stated (Yes).

l The questien does not have a single correct response (No).

Explanations of each of these categories are provided on the fo] lowing page.

i 1

! Continued Next Page

Familiar with Content?

Answer Yes if non-licensed operators participating in the operator licensing training program would be familiar with the question content. If you answer No, that non-licensed operators would not be familiar o

with the ocntent, please tell us the Reason why, usirrJ the following category codes:

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

Question Difficulty. Use the following definiticns to rate the difficulty of each question on a 1 through 7 scale:

very razy = A question that can be answered correctly by smoone who has Dat ocriplsted the fundamentals portion of the training programt.

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

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

i Question clearly Stated? If an item is clearly stated circle Yes. If it is un: lear or difficult to undarstard, circle No.

Sinsle Cune;t Response? If there is one and only cne correct answer, circle l

Yes for that quertion. If there is no clear correct answer, or if more than I

one response appears correct, please circle No.

l l

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

l l

, continumi Next Pae.ie

f LVAIUATICNS OF IUNDAME2frALS EXAMD&TICH QUESTIQtS l

I l

l Question

' Single Itam l

Familiar With lVery Vu' l clearly corrac.t Number l

Content?

l Easy Average Diftx ult l Stated?

l Response?

I I

I l

l If No, 11 l l

l l

l Yes/No l Reason l 1 2 3 4 5 6 7 Yes/No l Yes/No i

I I

l l

l 1

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

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

1 I

I 3

) Yus/No ll a, b, l1 2 3 4 5 6 7

.I Yes/No Yes/No 4

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

l 5

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

Yes/No Yes/No 6

l Yes/No

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

l I

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

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

Yes/No Yes/No i

)

9 l Yes/No l a, b, I

I 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

I I

i i

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

I I

l l

13 l Yes/No 1 a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 14 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No i

I I

I i

15 1 Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 16 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes#o 1

i i

l 1:

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

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

I l

L i

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

I I

l l

21 I Yes/No l a, b, 11 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

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

I i

1 l

25 l Yes/No I a, b, l1 2 3 4 5 6 7 Yes/No L Yes/No 26 l Yes/No l a, b, i1 2 3 4 5 6 7 1 Yes/No L Yes/No I

I I

k I

I C

! Continued Next Page I

t i

a I

Eyg}uations of M=antals Mm OMiers (cont'd)

I I

I Omstion Isin;1.

Item l

ramiliar with lvery very I clearly l correct Number l

Content?

l Easy Average Difficult l Stated?

l Response?

I I

I l

l If No 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 27 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 28 l Yr1/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yesgo l

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I 29

. 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 l

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I 31 Yes/No l a, b, 11 2 3 4 5 6 7 Yes/No Yes/No 32 Yes/No

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

I 33 ll Yes/No ll a, b, 1 2 3 4 5 6 7 l

Yes/No Yes#o i

34 l Yes/No

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

l 35 L Yes/No a, b, 1 2 3 4 5 6 7 I

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

Yes/No l Yes/No l

ll l

l 37 Yss/No l a, b, l1 2 3 4 5 6 7 Yes/No l Yes/No i

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

I l

1 39 l Yes/No l a, b, 1 2 3 4 5 6 7 4 Yes/No l Yes/No 40 l Yes/No l a, b, l1 2 3 4 5 6 7 ll Yes/No l Yes/No l

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I 41 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No Yes/No 42 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No Yes/No I

l l

1 43 l Yes/No l a, b,

,1 2 3 4 5 6 7 l Yes/No l Yes/No 44 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No I

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I l

45 l Yes/No l 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 YesAio l Yes/No i

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I l

47 l Yesyo l a, b, i1 2 3 4 5 6 7 l

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

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l l

49 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No 50 l Yes/No l a, b, l1 2 3 4 5 6 7 l Yes/No l Yes/No l

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centimed Next Page 1

GDDAL CUESTICES ABC17f 'DE RHDAMDTTAIS D:AMDRTICH l

In this section, we ask you to answer specific questions about each of I

the three sections in the exam (Ccsponents, Reactor Theory, and thenno-

{

dynamics) and s:re qaneral questions about the exam.

Some of the follow qaestions assuna that you have detailed infonnation about the Operator Licens Training Program.

If that is not true, please write "Do Not Know" for those gaestions.

For each statement appearirg below, please iniicate your response by circling Yes or No.

If you want to prwide ocminents about your responses to these items, please write them in the space below each item. You can also prwide adiitional coments about the exam in the last section.

i

]

Ccmoonents Ouestions (Itas 1 to 22) l P

Yes No 1.

Do the 22 exam questicms rispmsent a good measure of basic 1

Ctrpenents knowle$ge?

3 j

Yes No 2.

Do the 22 exam questions ocuprehensively sanple Orponents i

material presented in your operator Lioersing Training Program?

l I

a t

s

] heter 'Iheory Cuestions (Itms 23 to 36) l i

I Yes No 3.

Do the 14 exam questions rwpresent a good naasure of basic

[

3 Reactor Theory knowledge?

I Do the 14 exam qaestions otmprehensively sanple Reactor Theory i

i Yes No 4.

i j

material presented in your operator Licensirg Training i

Prtgram?

I I

i 2heITodyna. tics Questions (Itms 37 to 50) 1 i

3 Yes No 5.

to the 14 exam gaestions ripresent a gocd measure of basic i

W mamics knowlaije?

t 1

i Yes No 6.

Do the 14 exam gaestions ocmprehensively sanple Thermochnamics j

j natorial presental in ycur operator Licensing Training Program?

l i

i Yes No 7.

i Is it rmascmble to expect an iniividual with satisfactory knowlsige of the subject areas to ocrplete the Knismantals

{

i Dchm in two houm or less?

l i

1 I

{ 0:ntinued Next Pege l

1-.-

[eneral Questions about the Funhmentals Exam (cont'd)

Yes No 8.

Should more itru be added to this exam to ensure ocmprehensive coverage?

Yes No 9.

Can these knowlecQe armas be ocaprehensively tested with fewer items?

Yes No

10. After havirq reviewed this exem, do you believe that it is rw=ma7 for scneone have ocupleted all or part of the training program to obtain a score of 70% or higher?

Yes No

11. After having reviewed this exam, do you think non-licensed operators current *y participatifg in the operator training program ned to study to obtain a score of 70% or higher?

Yes No

12. Would you m--1 snd that a passing szza cn this exam be 4

requirst or all non-licensed operators prior to roceiving an y

NRC license?

Yes No

23. In general, is this exam too difficult? (Difficult is defined as containing many items that cannot be answered correctly by scneone who has ocmpleted the furdamentals portion of the operator training program.)

4 Yes No

14. In general, is this exam too easy? (Easy is defined as containing many items that can M answw ed corrwetly by m who has Dgt ocepleted the furdamentals portion of the operator training program.)

Yes Hu

15. Is the percentage of itens for the three sections agropriate for this exam (i.e., Ocmponents, 44%; Reactor 'Iheor!' 28%; and Wmmics, 28%)?

Yes M3

16. Does this exam measure knowledge required to s m '*aafully ocuplete the C+ sits, Reactor um ry, ard Mmmics sections of the operator trainirg program' Yes No

17. Is the material crwered in this exam presented early in your training prtgram?

. Contirund Next Page

e Yes No

18. In gemtral, do socnas on this exam repreact.t good indicator of i

how well an individual will perfore on the jrb as a licensed operator?

j Yes No

19. Do you feel that exam scores of 70% or higar indica'.:e that an individual has basic, fundamental knowledge of ' se attus?

General Ocaments If you have additional ocenents that you would like to make about the Funda-mentals Dcamination, please pIwide them below.

f t

b Thank you for your input. Please return this form to:

Ian Wiens U.S. NRC Mail Step OWIN 10-D 18 Washington, D-20555

.

ML20207K796

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Dear Mr. Rothert,

Enclosures:

Dear Mr. Syltia,

Enclosures:

Dear Mr. Raguse,

Enclosures:

Dear Mr. Antony,

Enclosures:

Dear Mr. Lazar,

Dear Mr. Neal,

Enclosures:

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