Text

NRC Operator Licensing Exam Rept 50-128/OL-96-02 Administered on 961119-21.Exam Results:Four Applicants Passed Exam & One Applicant Failed Exam
	ML20135E955
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Site:	05000128
Issue date:	12/03/1996
From:	Eresian W; NRC (Affiliation Not Assigned)
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U. S. NUCLEAR REGULATORY COMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-128/0L-96-02 FACILITY DOCKET NO.:

50-128 FACILITY LICENSE NO.:

R-83 FACILITY:

Texas A&M University EXAMINATION DATES:

November 19-21, 1996 EXAMINER:

Warr n J. Eresian, hief Examiner bl/QLLov 2 rJ i ctg (2

I 9d SUBMITTED BY:

Warren J. Eresi/n, Thief Examiner Date

SUMMARY

The NRC administered initial license examinations to five Reactor Operator applicants.

Four applicants passed the examination and one applicant failed the examination.

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ATTACHMENT 1 l

l 9612120257 961209 PDR ADOCK 05000128 V

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2 Rfp0P.T DETAILS j

1.

Exa91ners:

l'arren J. Eresian, Chief Examiner i

2.

Results:

R0 SR0 Total (Pass / Fail)

(Pass / Fail)

NRC Grading:

4/1 0/0 4/1 3.

Written Examination:

Four applicants passed the written examination. One applicant failed Category B but passed the examination overall.

4.

Operating Test:

All applicants passed the operating test.

5.

Exit Meeting:

An exit meeting was held on November 21, 1996.

Present were:

Warren J. Eresian, NRC Chief Examiner Mr. William Asher, Reactor Supervisor The NRC thanked the Texas A&M University staff for their assistance during the examination. No generic concerns were raised.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:

Texas A&M University i

REACTOR TYPE:

TRIGA DATE ADMINISTERED:

11/19/96 REGION:

4 CANDIDATE:

i INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the exam page itself, or the answer sheet provided.

Write answers one side ONLY.

Attach any answer sheets to the examination.

Points for each question are indicated in parentheses for each question. A 70%

in each category is required to pass the examination.

Examinations will be picked up three (3) hours after the examination starts.

% OF i

CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY

)

20 33.3 A. REACTOR THEORY.

THERMODYNAMICS. AND FACILITY OPERATING CHARACTERISTICS 20 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20 33.3 C. PLANT AND RADIATION MONITORING SYSTEMS 60 FINAL GRADE All work done on this examination is my own.

I have neither given nor received aid.

i Candidate's Signature ATTACHMENT @

. = _

NRC RUL R AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1.

Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

I 2.

After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination.

3.

Restroom trips are to be limited and only one candidate at a time may leave.

You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

4.

Use black ink or dark pencil only to facilitate legible reproductions.

5.

Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.

6.

Print your name in the upper right-hand corner of the answer sheets.

7.

The point value for each question is indicated in parentheses after the question.

8.

Partial credit may be given. Therefore. ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be given on multiple choice questions.

9.

If the intent of a question is unclear, ask questions of the examiner only.

10.

When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.

11.

When you are done and have turned in your examination, leave the examination area as defined by the examiner.

If you are found in this area while the examination is still in progress, your license may be denied or revoked.

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..=.-.

A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 3 QUESTION: 001 (1.00)

Inelastic Scatterina is the process whereby a neutron collides with a nucleus and:

recoils with the same kinetic energy it had prior to the collision.

a.

b.

recoils with a lower kinetic energy, with the nucleus emitting a j

gamma ray.

c.

is absorbed by the nucleus, with the nucleus emitting a gamma ray.

d.

recoils with a higher kinetic energy, with the nucleus emitting a i

gamma ray.

j QUESTION 002 (1.00)

{

1 An example of a fissile isotope which occurs naturally is:

a.

Pu-239 b.

U-238 c.

U-235 d.

Th-232 OUESTION: 003 (1.00)

Given:

Shutdown margin

$4.50 Control Rod 1

$2.00 Control Rod 2

$2.00 Control Rod 3

$1.00 l

What is the excess reactivity for this reactor?

a.

$0.50 b.

$1.50 c.

$2.50 d.

$5.00 l

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

l A. REACTOR lliEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 4 OUESTION: 004 (1.00) l During the time when reactor power decreases, the delayed neutron fraction. #:

a.

decreases because delayed neutron precursors are being produced at a slower rate.

b.

decreases because prompt neutrons are being produced at a slower rate.

c.

increases because delayed neutrons are being produced from precursors that were formed at the higher power level.

d.

remains unchanged.

l OUESTION: 005 (1.00)

When a reactor is oromot critical, the neutron multiplication rate is determined by:

a.

the generation time of prompt neutrons only, b.

the value of B,y.

c.

the generation time of delayed neutrons only, d.

the half-life of the shortest-lived delayed neutron precursor.

QUESTION: 006 (1.00)

The core of reactor A is in the form of a sphere of radius R.

The core of reactor B is in the form of a cube, with edge length R.

The neutron leakage from reactor B. compared to reactor A will be:

a.

greater than A.

b.

approximately the same as A.

c.

exactly the same as A.

d.

less than A.

1

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

O A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 5 OUESTION: 007 (1.00)

Which ONE of the following conditions would INCREASE the shutdown margin of a reactor?

a.

Inserting an experiment which adds positive reactivity.

b.

Lowering the moderator temperature, if the moderator temperature coefficient is negative.

c.

Depletion of burnable poison.

d.

Depletion of uranium fuel.

QUESTION: 008 (1.00)

When a reactor is scrammed, the xenon population starts to increase. This occurs primarily because:

a.

delayed neutrons are continuing to be produced and cause fissions.

resulting in xenon production.

b.

the half-life for the decay of I-135 is shorter than the half-life for the decay of Xe-135.

c.

Xe-135 is stable and does not decay.

d.

the neutron population is so low that xenon burnout does not occur.

QUESTION: 009 (1.00)

A reactor is operating at criticality.

Instantaneously, all of the delayed neutrons are suddenly removed from the reactor. The K,ff of the reactor in this state would be approximately:

a.

1.007 b.

1.000 c.

0.993 d.

0.000

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 6 OUESTION: 010 (1.00)

A reactor is critical at full rated power, with reactivity = zero. A control rod is inserted and the power decreases to a lower steady-state value.

The reactivity of the reactor at the lower power level is zero because:

a.

the positive reactivity due to the fuel temperature decrease balances the negative reactivity due to the control rod insertion.

4 b.

the negative reactivity due to the fuel temperature decrease equals the negative reactivity due to the control rod insertion.

1 c.

the positive reactivity due to the fuel temperature increase balances the negative reactivity due to the control rod insertion.

d.

the negative reactivity due to the fuel temperature increase equals the negative reactivity due to the control rod insertion.

QUESTION: 011 (2.00)

Given the following neutron life cycle for a critical reactor:

100 fast neutrons are produced from the previous generation and start to slow down.

20 neutrons are captured in resonance peaks, and 10 leak out of the core after they have reached thermal energy.

The remaining neutrons are absorbed in fuel and other materials. Each fission produces 2.5 neutrons, and 85% of the neutrons absorbed in fuel result in fissions.

For this reactor, the thennal utilization factor is:

a.

L.47 b.

0.62 c.

0.67 d.

1.613

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 7 i

OUESTION: 012 (1.00)

Which ONE of the following elements will slow down fast neutrons most quickly, i.e. produces the greatest energy loss per collision?

a.

Oxygen-16 b.

Uranium-238 c.

Hydrogen-1 d.

Boron-10 QUESTION: 013 (1.00)

A hypothetical fuel produces 20% of its power from the fission of element X and 80% of its power from the fission of element Y.

The beta fraction of element X 1s 0.006 and the beta fraction of element Y is 0.008. The beta fraction of the fuel as a whole is:

a.

0.0064 b.

0.0070

)

c.

0.0076 d.

0.0140 OUESTION: 014 (1.00)

An operating reactor generates 10" fissions per second.

The power of the reactor is approximately:

a.

16 kW b.

32 kW c.

48 kW d.

64 kW

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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6 Q

1 A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 8 00ESTION: 015 (1.00)

The Inhour Ecuation relates reactivity insertion p to reactor period. T.

Reartivity insertion A is +0.001 delta k/k. and reactivity insertion B is -0.001 1

de~

k/k.

The absolute value of the period will be:

a.

smaller for A.

4 b.

larger for A.

c.

smaller for B.

d.

the same for A and B.

QUESTION: 016 (1.00)

A 1/M curve is being generated as fuel is loaded into the core. After some fuel elements have been loaded, the count rate existing at that time is taken to be the new initial count rate.

C,.

Additional elements are then loaded and the i

inverse count rate ratio continues to decrease.

As a result of changing the initial count rate; a.

criticality will occur earlier (i.e. with fewer elements loaded.)

b.

criticality will occur later (i.e. with more elements loaded.)

c.

criticality will occur with the same number of elements loaded.

d.

criticality will be completely unpredictable.

QUESTION: 017 (1.00)

A reactor power calibration is being performed by measuring the rate of temperature increase in the reactor pool. Which ONE of the following conditions would result in calculated power being LESS THAN actual power?

a.

The measured final temperature is greater than the true temperature.

b.

The measured final temperature is less than the true temperature.

c.

The calculated volume of water in the pool is greater than the true volume.

d.

The calculated rate of temperature increase is greater than the true rate.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 9 OVESTION: 018 (1.00)

Delayed neutron precursors decay by beta decay. Which ONE reacti.on below is an example of beta decay?

s7 a.

Br

_, aa gg sa 33 s7 s6 b.

Br

,, asgp 33 87 86 c.

3 sbr

-> uKr 87 87 d.

3 sbr

- > 3sKr OUESTION: 019 (1.00)

Reactor A increases power from 10% to 20% with a period of 50 seconds. Reactor B increases power from 20% to 30% with a period of also 50 seconds. Compared to reactor A, the time required for the power increase of reactor B is:

a.

longer than A.

b.

exactly the same as A.

c.

approximately the same as A.

d.

shorter than A.

(***** END OF CATEGORY A *****)

B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 10 QUESTION: 001 (1.00)

The SRO on duty has directed you to " secure the reactor." This is done by:

a.

fully inserting all control rods and placing the rod control switches to NEUTRAL.

b.

scramming the reactor.

c.

removing all experiments.

d.

removing the reactor key from the control console.

QUESTION: 002 (1.00)

You observe a loss of reactor pool water which can be controlled by adding makeup water. In accordance with the Emergency Plan your first course of action is to:

a.

assess the severity of the pool water loss by observing the leakage rate and reactor bridge area radiation monitor readings.

b.

send a member of Reactor Operations to the west end of the pool and position the emergency cover over the 10-inch cooling exit line.

c.

dis)atch teams to take appropriate action to determine source of lea cage and correct by valve manipulation if possible.

d.

shutdown the reactor.

OUESTION: 003 (1.00) l InaccordancewithS0P"PersonnelDosimetry."anExpectedHighDoseIndividual is a person who:

a.

may receive a dose greater than the annual limit.

j b.

may receive a dose greater than 10% of the annual limit.

c.

will not be expected to exceed 10% of the annual limit.

d.

has received an unknown amount of radiation resulting from an accident.

i

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

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i B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 11 QUESTION: 004 (1.00)

In accordance with the Emergency Classi ication Guide, all alarms from the f

Facility Air Monitor System are classifi?d as Operational Events with the exception of:

a.

Stack Particulate Monitor.

b.

Building Gas Monitor.

c.

Fission Gas Monitor.

d.

Stack Gas Monitor.

QUESTION: 005 (1.00)

Which ONE of the following does not require the direct supervision (i.e.,

presence) of an SRO?

a.

Movement of the reactor bridge.

b.

Initiation of a pulse.

c.

Removal of a control rod.

d.

Performance of a power calibration of the Linear Power Channel.

OUESTION: 006 (1.00)

Which ONE of the following conditions is NOT permissible when the reactor is operating, or about to be operated?

a.

The reactivity worth of a single experiment = $1.00.

b.

A control rod scram = 1.5 seconds.

c.

An excess reactivity = $2.20.

d.

The Continuous Air Radiation Monitor is inoperable due to maintenance.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

S t

B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 12 OUESTION: 007 (1.00)

Limiting Safety System Settings:

a.

are limits on important process variables which are found to be i

necessary to reasonably protect the integrity of certain physical barriers which guard against the uncontrolled release of i

radioactivity.

b.

are settings for automatic protective devices related to those variables having significant safety functions.

i c.

are combinations of sensors. interconnecting cables or lines.

amplifiers, and output devices which are connected for the purpose i

of measuring the value of a variable.

d.

are the lowest functional capability or performance levels of equipment required for safe operation of the facility.

.i QUESTION: 008 (1.00)

The Total Effective Dose Equivalent (TEDE) is defined as the sum of the deep-dose equivalent and the committed effective dose equivalent. The deep-dose equivalent is related to:

a.

the dose to organs or tissues.

b.

the external exposure to the skin or an extremity.

4 c.

the external exposure to the lens of the eye.

d.

the external whole-body exposure.

QUESTICN: 009 (1.00)

An automatic scram signal which is NOT required by the Technical Specifications when operating in the steady state mode is:

a.

short period.

b.

high fuel temperature.

c.

high power level.

d.

loss of detector high voltage.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 13 l

l 1

QUESTION: 010 (1.00)

In accordance with 10CFR55, a licensed operator must:

i a.

pass a comprehensive requalification written examination and an annual operating test during a 24-month period.

b.

complete a minimum of six hours of shift functions each month.

c.

have a medical examination during the six-year term of the license.

d.

notify the NRC within 30 days following an arrest.

QUESTION: 011 (1.00)

Operation of the reactor in the steady state mode means that:

a.

the mode switch is in the steady state position.

b.

reactor power is constant.

c.

reactor power is constant, with power controlled by the servo system.

d.

the mode switch is in the steady state position with power at 1 MW,

)

OUESTION: 012 (1.00)

A " Red Tag" can only be initiated by:

a.

the SR0 on duty.

b.

any SRO.

c.

any NSC staff member.

d.

the Manager of Reactor Operations.

i

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

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l B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 14 QUESTION: 013 (1.00)

In accordance with 10CFR20. the " Derived Air Concentration (DAC) refers to:

a.

the amount of radioactive material taken into the body by inhalation or ingestion in one (1) year which would result in a committed l

effective dose equivalent of five (5) rems.

1 b.

limits on the release of effluents to an unrestricted environment.

l c.

the dose equivalent to organs that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.

d.

the concentration of a given radionuclide in air which if breathed for 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, would result in a committed effective dose equivalent of five (5) rems.

1 QUESTION: 014 (1.00)

You are standing ten (10) feet from a point source of radiation. When a k inch sheet of lead is placed between you and the source, your exposure rate is halved.

How many sheets of lead are required to reduce your exposure rate to 1% of its original value?

a.

2 b.

6 l

c.

7 d.

10 OUESTION: 015 (1.00)

Information regarding the assembly and location of each fuel bundle is found in the:

a.

fuel log.

b.

operations log.

c.

supervisor log.

d.

reactor data log.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

l

l B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 15 j

QUESTION: 016 (1.00)

"The temperature in a TRIGA-FLIP fuel element shall not exceed 2100 F (1150 C) under any conditions of operation." This is an example of a:

a.

safety limit.

b.

limiting safety system setting.

i c.

limiting condition for operation.

d.

surveillance requirement.

QUESTION: 017 (1.00)

The Design Basis Accident for the TA&M reactor is:

a.

an accidental pulse at full power.

b.

a loss of coolant accident (reactor pool is accidentally drained of i

water).

c.

the loss of integrity of one fuel element cladding and the simultaneous loss of pool water.

d.

the accidcotal insertion of an experiment with a positive reactivity worth of $1.00 while the reactor is critical.

QUESTION: 018 (1.00)

An experiment with a reactivity worth of $0.40 is to be removed from the core.

Prior to performing this operation:

l a.

reactor power must be less than 600 kW.

l l

b.

the reactor must be subcritical.

l c.

the reactor must be subcritical by at least $0.40.

d.

the reactor must be shutdown.

4

)

J

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

l

B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 16 0UESTION: 019 (2.00)

Match each of the following actions in Column I with the correct term from the Technical Specifications in Column II: Channel Check, Channel Test, or Channel Calibration.

(Only one term per action).

Column I Column II a.

Immersing a thermometer in an ice

1. Check bath, then in boiling water and noting the output.

2. Test b.

Placing a source next to a radiation

3. Calibration detector and observing meter movement.

c.

Performing a determination of reactor power with a heat balance, then adjusting a aower meter to correspond to the heat Jalance.

d.

Observing the overlap between two different neutron detectors as power increases.

l l

l

(***** END OF CATEGORY B *****)

l

C.

PLANT AND RADIATION MONITORING SYSTEMS Page 17 OVESTION: 001 (1.00)

Which ONE of the following provides a reactor scram in any mode of operation?

l a.

High fuel temperature.

b.

Low pool level.

c.

High power level.

d.

Loss of supply voltage to high power level detector.

QUESTION: 002 (1.00)

When the reactor is being controlled by the servo controller:

a.

the period scram is bypassed.

b.

the regulating rod moves in response to the linear channel signal.

c.

the regulating rod moves in response to the log power channel signal.

d.

the regulating rod moves out following a scram to try to maintain constant power.

j OUESTION: 003 (1.00)

The reactor is in the " PULSE" mode when the TR fire button is depressed.

As a result, the solenoid valve is:

a.

energized. admitting air to the cylinder.

b.

de-energized, admitting air to the cylinder.

c.

de-energized, removing air from the cylinder.

d.

energized, removing air from the cylinder.

4

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C.

PLANT AND RADIATION MONITORING SYSTEMS Page 18 OVESTION: 004 (1.00)

A safety plate assembly is installed beneath the reactor grid plate. Its purpose l

is to:

l a.

stop a standard fuel element from dropping more than 2 inches out of the core if it should become detached from its mounting.

b.

stop a FLIP fuel element from dropping more than 2 inches out of the core if it should become detached from its mounting.

c.

stop a control rod follower from dropping more than 2 inches out of the core if it should become detached from its mounting.

d.

provide a stop for the grid plate if it should become detached from 1

the suspension frame.

QUESTION: 005 (2.00)

For the items labeled A through D on Figure 1. select the proper component from the item list in Column II. Only one answer may occupy a space in column I.

(4 required at 0.50 each).

Column I (Figure label)

Column II (Item list)

A.

1. Electromagnet l

B.

2. Armature Connector i

C.

3. Ergage Switch D.

4. Control Rod Barrel

5. Armature

6. Piston l

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C.

PLANT AND RADIATION MONITORING SYSTEMS Page 19 OUESTION: 006 (1.00)

For a control rod, the "CARR UP" light is 0FF. the "CARR DOWN" light is 0FF and the " ENGAGED" light is ON. This indicates that:

a.

the rod and drive are in contact, and are both full in, b.

the rod and drive are in contact, and are both full out.

c.

the rod and drive are not in contact, and the rod and drive are somewhere between full in and full out.

d.

the rod and drive are in contact, and are somewhere between full in and full out.

QUESTION: 007 (1.00)

Under emergency conditions, the master control panel located in the reception room may be used to:

a.

scram the reactor, b.

operate the air handling systems.

c.

operate the emergency pool fill system.

d.

operate the emergency lighting system.

OUESTION: 008 (1.00)

The FLIP fuel elements:

a.

are about 20% enriched uranium with stainless steel clad and no burnable poison.

b.

are about 70% enriched uranium with stainless steel clad and erbium burnable poison.

c.

are about 20% enriched uranium with aluminum clad and erbium burnable poison.

d.

are about 70% enriched uranium with aluminum clad and no burnable poison.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

C.

PLANT AND RADIATION MONITORING SYSTEMS Page 20 QUESTION: 009 (1.00)

Which ONE of the following controls the amount of reactivity that is inserted by the transient rod during pulse operations?

a.

The preset pulse timer setting that vents the pneumatic piston.

b.

The pressure of the air applied to the pneumatic piston.

c.

The position of the cylinder.

d.

The reactivity of the reactor prior to firing the pulse.

QUESTION: 010 (1.00)

The purpose of the diffuser above the core during operation is to:

a.

reduce dose rate at the pool surface from N-16.

b.

enhance heat transfer across all fuel elements in the core.

c.

better distribute heat throughout the pool.

d.

ensure consistent water chemistry in the core.

QUESTION: 011 (1.00)

When the stack particulate activity alarm sounds, which ONE of the following occurs?

a.

The reactor scrams.

b.

The evacuation alarm sounds.

c.

The air handling system shuts down.

d.

There are no automatic actions.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

O C.

PLANT AND RADIATION MONITORING SYSTEMS Page 21 OUESTION: 012 (2.00)

Match the neutron measuring channel in Column A with the type of detector in Column B.

Detectors in Column B may be used once, more than once, or not at all.

Column A Column B a.

Log Power Channel 1.

Compensated Ion Chamber b.

Linear Power Channel 2.

Uncompensated Ion Chamber c.

Safety Power Channel 3.

Fission Chamber d.

Pulse Power Channel 4.

G-M Tube OUESTION: 013 (1.00)

More than 95% of the facility's Ar-41 is produced:

a.

in the beam ports.

b.

in the pneumatic system.

c.

in the reactor building atmosphere.

d.

in the reactor pool.

QUESTION: 014 (1.00)

The reactor is operating at 800 kW, with power being controlled by the servo control system. An experiment is inadvertently inserted into the core, causing reactor power to drop to 600 kW.

As a result:

a.

the regulating rod moves out of the core in an effort to restore power to 800 kW.

b.

the reactor scrams, c.

regulating rod control shifts back to manual.

d.

the regulating rod moves into the core to maintain power at 600 kW.

l

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

1

O C.

PLANT AND PADIATION MONITORING SYSTEMS Page 22 QUESTION: 015 (1.00) j The chemical feed system controls the chemical characteristics of the:

i a.

secondary cooling loop.

j b.

pool water cooling system.

i c.

purification system.

d.

pool water transfer system.

QUESTION: 016 (1.00)

Which ONE of the following statements correctly describes the purpose of the synchronous transmitter in the control rod drive assembly, a.

Provides rod position indication when the electromagnet engages the connecting rod armature.

b.

Provides a variable voltage to the rod drive motor for regulating control rod speed.

c.

Provides potential voltage as required for resetting the electromagnet current.

d.

Provides the potential voltage to relatch the connecting rod to the electromagnet.

QUESTION: 01)

(1.00)

Thermocouples in the instrumented fuel element measure temperature at the:

a.

interior surface of the cladding, b.

center of the zirconium rod.

c.

outer surface of the fuel.

d.

interior of the fuel..

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

a C.

PLANT AND RADIATION MONITORING SYSTEMS Page 23 QUES fl0N: 018 (1.00)

When a compensated ion chamber is used for neutron detection at low power levels, how is the gamma flux accounted for?

a.

The gamma flux is cancelled by creating an equal and opposite gamma current.

b.

The gamma flux is proportional to neutron flux and is counted with the neutrons.

2 c.

Pulse height discrimination is used to eliminate the gamma flux.

1 d.

The gamma flux passes through the detector with no interaction because of detector design.

1

(***** END OF CATEGORY C *****)

(***** END OF EXAMINATION *****)

1

f 1

1 4-4

+

l l

c s

-s ha

!:I

!,/C l

/ -

A i

\\,!

'A l

1 l

r 3

'N l

I 1:

i i

i l

I

(-

J

l l l

_h_!

!b ND t

i 1

I

-<D FIGURE I

SHIM-SAFETY ARMATURE AND DAMPENING DEVICE ASSEMBLY t

l

l EQUATION SHEET 0 = m c, AT CR (1-Keff)3 = CR (1-Keff)2 3

2 SUR = 26.06/r P = P 10""

o P = P e"'"

r - (t*/p) + [(B-p)/A,,fp]

o A,,,= 0.1 seconds ~2 DR D 2 = DR D

33 22 DR = DR e'"

DR = 6CiE/D 2

o 0 = (Keff-1)/Keff 1 eV = 1.6x10 " watt-sec.

20 1 Curie - 3.7x10 dps 1 gallon water - 8.34 pounds 1 Btu - 778 ft-lbf F = 9/5 C + 32 6

1 Mw - 3.41x10 BTU /hr C = 5/9 ( F - 32)

I

A.

REACTOR THEORY THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)

If you change your answer, write your selection in the blank.

001 a

b c

d 002 a

b c

d 003 a

b c

d 004 a

b c

d 005 a

b c

d 006 a

b c

d 007 a

b c

d 008 a

b c

d 009 a

b c

d 010 a

b c

d 011 a

b c

d 012 a

b c

d l

013 a

b c

d 014 a

b c

d 015 a

b c

d 016 a

b c

d 017 a

b c

d 018 a

b c

d 019 a

b c

d

(***** END OF CATEGORY A *****)

B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS

. ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice) l If you change your answer, write your selection in the blank.

I l

001 a

b c

d 002 a

b c

d 003 a

b c

d l

004 a

b c

d 005 a

b c

d 006 a

b c

d 007 a

b c

d 008 a

b c

d 009 a

b c

d 010 a

b c

d 011 a

b c

d 012 a

b c

d 013 a

b c

d 014 a

b c

d 015 a

b c

d 016 a

b c

d 017 a

b c

d 018 a

b c

d 019 a

b c

d

(***** END OF CATEGORY B.*****)

C.

PLANT AND RADIATION MONITORING SYSTEMS ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)

If you change your answer, write your selection in the blank.

001 a

b c

d 002 a

b c

d 003 a

b c

d l

004 a

b

.c d

005 a

b c

d 006 a

b c

d 007 a

b c

d 008 a

b c

d 009 a

b c

d 010 a

b c

d 011 a

b c

d 012 a

b c

d 013 a

b c

d 014 a

b c

d l

015 a

b c

d l

016 a

b c

d 017 a

b c

d l~

018 a

b c

d l

J

(***** END OF CATEGORY C *****)

4

l A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS ANSWER: 001 (1.00)

B.

REFERENCE:

R. R. Burn. Introduction to Nuclear Reactor Operations, pg. 2-28.

ANSWER: 002 (1.00)

C.

REFERENCE:

Lamarsh. Introduction to Nuclear Engineering. 2nd Edition, pg.104.

ANSWER: 003 (1 00)

A.

i

REFERENCE:

C.

REcERENCE:

R. R. Burn. Introduction to Nuclear Reactor Operations, pg. 2-45.

ANSWER: 013 (1.00)

C.

REFERENCE:

R. R. Burn. Introduction to Nuclear Reactor Operations, pg. 3-11.

The beta fraction for the fuel is the power weighted average of the beta fractions for each component.

Beta - (0.2)(0.006) + (0.8)(0.008) = 0.0076 ANSWER: 014 (1.00)

B.

REFERENCE:

R.R. Burn.IntroductiontoNuclearReactorOp9erations, pg. 2-51.

(10'S fissions /sec)x(200 Mev/ fission)x(1.6x10- watt-sec/ev) = 32 kW.

ANSWER: 015 (1.00) i A.

REFERENCE:

Lamarsh. Introduction to Nuclear Engineering. 2nd Edition, pg. 285.

ANSWER: 016 (1.00)

C.

1

REFERENCE:

B.

REFERENCE:

SDP Personnel Dosimetry.

ANSWER: 004 (1.00)

C.

REFERENCE:

Emergency Classification Guide, pg. 2.

ANSWER: 005 (1.00)

D.

TA&M Requalification Program.

l

I

REFERENCE:

SAR, page 119.

i i

ANSWER: 012 (2.00)

A,3: B.1: C.2: 0,2 i

REFERENCE:

SAR, pages 91-96.

ANSWER: 013 (1.00)

D.

ML20135E955

Text

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