Text

NRC Operator Licensing Exam Rept 50-128/OL-97-02 Including Completed & Graded Tests for Tests Administered on 970825- 26.Exam Results:One RO & One SRO Passed Exam.Two ROs Failed Exam
	ML20217B215
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Site:	05000128
Issue date:	09/03/1997
From:	Eresian W; NRC (Affiliation Not Assigned)
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c LS. NUCLEAR PEGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50 In8/OL 97 02 FACILITY DOCKET NO.:

50 128 FACILITY LICENSE NO.:

R 23 FACILITY:

Texas A&M University EXAMINATION DATES:

August 25 26,1997 EXAMINER:

Warren J. Eresian, Chief Examiner SUBMITTED BY:

eXAcc w f6 _ 9 J f

Warren J. Ereslin, Chief Examiner' Date

SUMMARY

The NRC administered initiallicense examinations to one Rsactor Operator applicant and one Senior Reactor Operator (Instant) applicant. All applicants passed the examination.

AffACMMENT 1 9709230272 970904 PDR ADOCK 05000128 V

PDR j

I

]

2-REPORT DETAILS 1.

Examiners:

Warren J. Eresian, Chlef Examiner 1

4 1

2.

Results:

RO SRO Total (Pass / Fall)

(Pass / Fall)

NRC Grading:

1/0 1/0 2/0 4

3.

Written Examination:

All applicants passed the written examination.

4.

Operating Test:

(

j All applicants passed the operating test.

5.

Exit Meeting:

An exit meeting was held on August 26,1997. Present were:

Warren J. Eresian, NRC Chief Examiner 4

Alfred Sanchez, Reactor Administrative Assistant i

The NRC thanked the Texas A&M University staff for their cooperation during the j

examinations. No generic concerns were noted.

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

Texas A&M University REACTOR TYPE:

TRIGA DATE ADMINISTERED:

8/25/97 REGION:

4 CANDIDATE:

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 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 rqy own. I have neither given nor received aid.

Candidate's Signature ATTACHMENT 2

NRC RULES 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.

2.

After the examination has been completed, you must sign the statement on the cover sheet indicatir.g 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 the examination cover sheet. provided in the upper right hand corner of 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 e 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 area while the examination is still in progress, you are found in thisyour license may denied or revoked.

=6

A. REACTOR THEORY. THERMDDYNAMICS AND FAClllTY OPERAT]NG CHARACTER!STICSPage 3 00EST10N: 001 (1.00)

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

a.

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

recoils with a lower kinetic energy, with the nucleus emitting a gamma ray, c.

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

d.

recoils with a higher kinetic energy, with the nucleus emitting a gamma ray.

QUESTION: 002 (1.00)

A reactor is suberitical with a K,, delta k/k). A positive reactivity of $5.00 is of 0.955.

inserted into the core (S = 0.001 At this point. the reactor is:

a.

supercritical b.

exactly critical.

c.

prompt critical, d.

suberitical.

QUESTION: 003 (1.00)

Given:

Excess reactivity

$0.50 Control Rod 1

$2,00 Control Rod 2 52.00 Control Rod 3

$1.00 What is the actual shutdown margin (not Tech. Spec. minimum) for this reactor?

a.

50.50 b.

$2.50 c.

$4.50 d.

$5.00

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

b A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 4 OVEST10N: 004 (1.00)

During the time when reactor power increases, the delayed neutron fraction. S:

a.

increases because delayed neutron precursors are being produced at a faster rate.

b.

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

increases because delayed neutrons are bein produced from c.

precursors that formed at the higher power level,g d.

remains unchanged.

OVESTION: 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,,,.

c.

the generation time of delayed neutrons only.

d.

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

QUESTION: 006 (1.00)

The term

buckling" in a reacter refers to:

a.'

the ratio of average neutron flux to maximum neutron flux.

b.

the ratio of reflected neutron flux to average neutron flux, c.

the curvature of the neutron flux.

d.

self-shielding.of reactor fuel.

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

.---4 r

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l A. REACTOR THEORY. THERMODYNAMICS AND FAClllTY OPERATING CHARACTERISTICSPage 5 l

OVEST10N: 007 (1.00)

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

a.

Inserting an experiment which adds negative reactivity.

b.

Increasing the moderator temperature if the moderator temperature coefficient is negative, c.

Depletion of burnable poison.

d.

Depletion of uranium fuel.

OVEST10N: 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 Km 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 *****)

A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 6 OVEST10N: 010 l1,00)

A reactor is critical at 50% of rated power, with reactivity = 2ero. A control rod is withdrawn and the power increases to a higher steadybecause:

state value.

The reactivity of the reactor at the higher power level is zero a,

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

b.

the negative reactivity due to the fuel temperature decrease equals the positive reactivity dtie to the control rod withdrawal.

c.

the positive reactivity due to the fuel temperature increase balances the negative reactivity due to the control rod withdrawal, d.

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

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 thermal utilization factor is and the resonance escape probability is a.

0.47. 0.70 b.

0.62, 0.90 c.

0.67, 0.80 d.

1.613, 0.80

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

__--__J

1 A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTER!STICSPage 7 1

l 00EST10N: 012 (1.00)

Which ONE of the following elements will slow down fast neutrons least quickly.

i.e. produces tne smallest energy loss per collision?

a.

Oxygen 16 b.

Uranium 238 c.

Hydrogen 1 d.

Boron 10 i

1 1

OVEST10N: 013 (1.00) i A reactor fuel consisting of U 235 and U 238 is 20% enriched. This means that:

a.

20% of the weight of the fuel consists of U 235, b.

20% of the volume of the fuel consists of U 235.

i c.

the ratio of U 235 atoms to U 238 atoms is 20%

d.

20% of the atoms of the fuel consists of U 235.

i OVESTION: 014 (1.00) j Which ONE of the reactions below is an example of a ohotoneutron source?

H' + y -> 3H' + n a.

3 l

b.

0 " -> 3 r" + pla!" + 3n + y 2

B

,2 Sb '3 + n -> $3Sb + y 2

2 c.

53 d.

.Be' + a -> C ' + n 2

t

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

i 1

A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 8 s

OUEST10N: 015 (1.00)

The Inhour Ecuation relates reactivity /k and reactivity insertion B is 0.00 insertion p to reactor period. T.

Reactivity insertion A is +0.001 delta k delta k/k.

The absolute value of the period will be:

l a.

smaller for A.

I b.

larger for A.

c.

smaller for B.

d.

the same for A and B.

l OVEST10N: 016 (1.00)

A 1/H curve is being generated as fuel is loaded into the core, After some fuel 4

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 inverse count rate ratio continues to decrease.

As a result of changing the initial count rate:

a, criticali'r will occur earlier (i.e. with fewer elements loaded.)

1

/

b.

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

c.

criticality will occur with the same number of elements loaded.

j d.

criticality will be completely unpreaictable.

QUESTION: 017 (1.00)

A reactor power calibration is being performed by measuring the rate of te erature increase in the reactor pool. Which ONE of the followin wou.d result 'in calculated power being GREATER THAN actual power? g conditions 4

a.

The measured initial temperature is greater than the true temperature.

b.

The measured final temperature is greater than the true temperature, c.

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

d.

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

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

s e

A. REACTOR THEORY THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 9 OVEST10N: 018 (1.00)

Which ONE of the following does NOT affect the Effective Multiplication Factor Km e

a.

The moderator to fuel ratio.

b.

The moderator temperature.

c.

The physical dimensions of the core, d.

The strength of an installed neutron souce.

OVEST!DN: 019 (1.00)

Reactor A increases power from It to 21 in 50 seconds. Reactor B increases power from 2% to 3% also in 50 seconds. Compared to reactor A. the period of the power increase of reactor B is:

a.

longer than A.

b.

exactly the same as A.

c.

75% of A.

d.

shorter than A.

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

4

u B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 10 OVEST10N: 001 (1.00)

A reactor parameter which is protected by a Safety Limit is:

a.

reactor power.

b.

fuel element temperature, c.

fuel cladding temperature.

d.

pool water level.

OVEST10N: 002 (1.00)

A person has received a serious injury which does not involve contamination. In accordance with the Emergency Plan, your.f.1rit course of action is to:

a.

notify the SR0 on duty, b,

call for an ambulance, briefly describe the injury and explain the type of accident, c,

go to the injured person and assess the extent of the injury.

d.

shutdown the reactor.

OVESTION: 003 (1.00)

An Emergency Action Level is:

a.

a condition which calls for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.

b.

a class of accidents for which predetermined emergency measures should be taken or considered.

c.

a specific instrument reading or observation which may be used as a threshold for initiating appropriate emergency procedures.

d.

a procedure that details the implementation actions and methods required to achieve the objectives of the emergency plan.

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

- i=-..

___-_m._m-

B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 11 OVEST10N: 004 (1.C 0)

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

presence) of an SRO?

a.

Hovement of the reactor bridge, b.

F,itiation of a pulse.

c.

Removal of a control rod.

d.

Performance of a power calibration of the Linear Power Channel.

QUESTION: 005 (1.00)

Which ONE of the following conditions is permissible when the reactor is operating or about to be operated?

a.

Steady state power level of 1.2 megawatts for purposes of testing, b.

A non secured experiment worth $1.50.

c.

A fuel element is known to be damaged, but has been moved to the edge of the core.

d.

The Continuous Air Radiation Monitor and the Exhaust Gas Radiation Monitor are inoperable due to maintenance and have been replaced with gamma sensitive instruments with alarms.

QUESTION: 006 (1.00)

Limiting Safety System Settings:

a.

are limits on important process variables which are found to be necessary to reasonably protect the integrity of certain physical barriers which guard against the uncontrolled release of radioactivity.

b.

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

are combinations of sensors, interconnecting cables or lines, amplifiers, and output devices which are connected for the purpose 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.

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

B.

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

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

Prior to performing this operation:

a.

reactor power must be less than 600 kW.

b.

the reactor must be subtritical, c.

the reactor must be subcritical by at least $0.40.

d.

the reactor must be shutdown.

QUESTION: 008 (1.00)

A " Red Tag" can only be initiated by:

a.

the SRO on duty, b.

any SRO.

c.

any NSC staff member, d.

the Manager of Reactor Operations.

QUESTION: 009 (1.00)

A power calibration (calorimetric) of the linear power channel has been performed.

In order to make the front panel meter indication agree with the calculated power:

a.

the compensating voltage of the linear channel CIC is adjusted, b.

the high voltage of the linear channel CIC is adjusted, c.

the position of the linear channel CIC is adjusted, d.

the full power gain adjust potentiometer is adjusted.

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

4 B.

NORMAL / EMERGENCY PROCEDURES & FAD 10 LOGICAL CONTROLS Page 13 OVEST10N: 010 (1.00)

A startup checklist has been completed and a startup 3erformed. The reactor is then shutdow'n (scheduled.) During the shutdown, the aridge is moved. When the reactor is again started up:

a.

another complete checklist is required, b.

only section A of the checklist is required.

c.

the scram circuits must be checked.

d.

only section D of the checklist is required.

QUESTION: 011 (1.00)

In accordance with 10CFR20. the " Annual Limit on Intake (All)" 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 effective dose equivalent of five (5) rems, b.

limits on the release of effluents to en unrestricted environment.

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.

QUESTION: 012 (1.00)

The dose rate from a mixed beta gama source is 100 mrem / hour at a distance of one (1) foot, and is 0.1 mrem / hour at a distance of twenty (20) feet.

What percentage of the source consists of beta radiation?

a, 20%,

b.

40%.

c.

60%.

d.

80%.

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

L B.

NORMAL / EMERGENCY PROCEOURES & RADIOLOGICAL CONTROLS Page 14 OVEST10N: 013 (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.

QUESTION: 014 (1.00)

"The total annual discharge of Argon 41 into the environment may not exceed 30 Ci per year unless permitted by the RSB." This is an example of a:

a.

safety limit, b.

limiting safety system setting, c.

limiting condition for operation.

d.

surveillance requirement.

QUESTION: 015 (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 *****)

=__

=

8

I B.

NORMAL / EMERGENCY PROCE0VRES & RADIOLOGICAL CONTROLS Page 15 OVEST10N: 016 (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.

OVESTION: 017 (2.00)

Select the MODE from Column 11 when the Safety Channels from Column I are required to be operable. Modes may be used once, more than once, or not at all.

Column 1 Column II (Safety Channel)

(Mode) a.

Fuel Element Temperature 1.

Steady State only b.

Preset timer 2.

Both modes c.

Transient Rod Position 3.

Pulse only d.

. Log Power OVESTION: 018 (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.

scraming the reactor, c.

removing all experiments, d.

removing the reactor key from the control console.

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

B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 16 OVESTION: 019 (1.00)

In accordance with the Emergency Classification Guide, all alarms from the Facility Air Monitor System are classified as Operational Events with the exception of:

a.

Stack Particulate Monitor.

b.

Building Gas Monitor.

c.

Fission Gas Monitor.

d.

Stack Gas Monitor.

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

C.

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

The Log Power Channel consists of a(n) and provides an input to the a.

Ion Chamber: period circuit, b.

Compensated Ion Chamber: low count rate (2 cps) interlock.

l c.

Fission Chamber: servo controller.

d.

Fission Chamber: I kW pulse interlock.

l OVESTION: 002 (1.00)

Which ONE of the following statements is NOT TRUE regarding the Servo Flux Control syttem?

a.

Pressing the Gang Up/ Gang Down switch will turn off the servo unit, 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.

If power level drifts +/- 5% of the setpoint the servo unit will turn off.

QUESTION: 003 (1.00)

A three way solenoid valve controls the air supplied to the pneumatic cylinder of the transient rod. De energizing the solenoid causes the valve to shift to:

a.

open, admitting air to the cylinder.

b.

close, admittirg air to the cylinder, c.

open, removing air from the cylinder, d.

close, removing air from the cylinder.

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

e C.

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

A 13/4 inch diameter hole through the grid plate is located at the southwest corner of the four rod fuel assemblies. The purpose of these holes is to:

a.

accomodate a fuel followed control rod.

b.

provide a mounting location for in core experiments.

c.

allow for accurate repositioning of the reactor core which is essential for numerous experiments, d.

provide a coolant flow path through the grid plate.

O'JESTION: 005 (2.00)

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

(8 required at 0.25 each).

Column I (Fiaure label)

Column II (item list)

A.

1. Synchronous Transmitter B. _, _,

2. Electromagnet C.

3. Engage Switch D.

4. Motor E.

5. Down Switch F.

6. Low Speed Gearbox G.

7. Jam Switch H.

8. High Speed Gearbox

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

1 C.

PLANT AND RADIATION MONITORING SYSTEMS Page 19 OVEST10N: 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.

OVESTION: 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.

QUESTION: 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 I

poison.

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

C.

PLANT AND RADIATION HONITORING 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 *****)

i

4 C.

PLANT AND RADIATION HONITORING SYSTEMS Page 21 OVEST10N: 012 (2.00)

Match the radiation 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.

Stack Gas (Ar-41) Monitor 1.

lon Chamber b.

Fission Product Monitor 2.

Proportional Counter c.

Area Radiation Hon'itor 3.

Scintillation Detector d.

Reactor Building Gas Monitor 4.

G M Tube QUESTION: 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 n.)ves 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.

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

C.

PLANT AND RADIATION HONITORING SYSTEMS Page 22 OVEST10N: 015 (1.00)

The chemical feed system controls the chemical characteristics of the:

a.

secondary cooling loop.

b.

pool water cooling system, 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: 017 (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 *****)

l l

C.

PLANT AND RADIATION MONITORING SYSTEMS.

Page 23 OVESTION: 018 (1.00)

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

a.

The gama flux is cancelled by creating an equal and opposite gama

current, b.

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

Pulse height discrimination is used to eliminate the gamma flux.

d.

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

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

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

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

A.

REFERENCE:

A R. R. Burn. Introduction to Nuclear React a Operations, pg. 2-28.

-ANSWER: 002 (1.00)

D.

REFERENCE:

7 Lamarsh. Introduction tc Nuclear Engineering. 2nd Edition. 39. 282.

?

$5.00 - 0.035 delts k/k.

Since the times are the same, power increase B requires a longer period.

e

I B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS ANSWER: 001 (1.00)

B.

REFERENCE:

SAR, page 92.

-ANSWER: 002 (1.00)

C.

SAR page 68.

4 -

-ANSWER: 011- (1.00)

C.

REFERENCE:

SAR page 119.

ANSWER: 012 (2.00)

A.3:-B.3: C 4: D3

SAR page 65.

ANSWER:~016 (1.00)

A.

REFERENCE:

SAR. page 26.

ANSWER: 017 (1.00)

D.

REFERENCE:

SAR page 18.

ANSWER: 018 (1.00)

A.

REFERENCE:

50P Linear Power Measuring Channel Maintenance Surveillance.

A.

REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS ANSWER SHEET MULTlFLE 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 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 *****)

l

3-..

B.

NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS 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 1

009 a

b c

d 010 a

b c

d 011 a

b c

d 012 a

b c

d 015 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 104D RADIATION HONITORING 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 004 a

b c

d 005 a

b c

d e

f g

h 006 a

b c

d 007 a

b c

d i

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

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

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

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

P = Po e"")

7 = (f*/p) + [(S-0)/A,,p]

A,,, a 0.1 seconds'2 DR 0 2 - DR D '

33 22 DR = DR e

DR = 6CiE/Dr o

p = (Keff-1)/Keff l' eV = 1.6x10'" watt-sec.

1 Curie = 3.7x10 ' dps 1 gallon water = 8.34 pounds 2

1 Btu,= 778 ft-lbf

F = 9/5*C + 32 5

1 N = 3.41x10 BTV/hr

C = 5/9 (*F - 32)

.,..19...

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