ML20128J088

Exam Rept 50-188/OL-96-01 on 960924-25.Exam Results:All Applicants Passed Exam

ML20128J088
Person / Time
Site:	Kansas State University
Issue date:	10/02/1996
From:	Eresian W NRC (Affiliation Not Assigned)
To:
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ML20128J078	List: ML20128J088
References
50-188-OL-96-01, 50-188-OL-96-1, NUDOCS 9610100180
Download: ML20128J088 (34)

Text

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V.'S. NVCLEAR REGULATORY COMMISSION  !

OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-188/0L-96-01 FACILITY DOCKET NO.: 50-188 FACILITY LICENSE N0.: R-88 FACILITY: Kansas State University EXAMINATION DATES: September 24-25, 1996 l

' I EXAMINER: Warren J. Eresian Chief Examiner SUBMITTED BY: h 2 ,' h WaTren J. Eres/an, Chief Examiner

/c!L!94Date l

SUMMARY

1 The NRC administered initial license examinations to one Senior Reactor Operator (Upgrade) applicant and two Reactor Operator applicants. All applicants passed the examination.

ATTACHMENT 1 9610100180 961007 8 PDR ADOCK 0500

I REPORT DETAILS l

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1. Examiners:

l l Warren J. Eresian, Chief Examiner

2. Results:

R0 SR0 Total j (Pass / Fail) (Pass / Fail) (Pass / Fail)

NRC Grading: 2/0 1/0 3/0 a

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3. Written Examination:  ;

i Both Reactor Operator applicants passed the written examination. The examination was waived for the Senior Reactor Operator (Upgrade) j applicant.

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4. Operating Test:

f All applicants passed the operating test.

5. Exit Meeting

An exit meeting was held on September 25, 1990. Present were

Warren J. Eresian, NRC Chief Examiner Mr. Brendan Ryan, Reactor Supervisor l The NRC thanked the Kansas State University staff for their assistance

] during the examination. No generic concerns were raised.

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U. S'. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Kansas State University REACTOR TYPE: TRIGA DATE ADMINISTERED: 09/24/96 REGION: 4 l 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.

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

in each category is required to pass the examination.

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

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

CATEGORY

! 20 35 A. REACTOR THEORY.

THERMODYNAMICS. AND FACILITY OPERATING CHARACTERISTICS 18 32 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 19 33 C. PLANT AND RADIATION MONITORING SYSTEMS 57  %

_. FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

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NRC RULES ANDyGUIDELINES FOR LICENSE EXAMINATIONS i

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 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. THERM 0bYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 3 OUESTION: 001 (1.00) 1 Inelastic Scatterino is the process whereby a neutron collides with a nucleus and -

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a. recoils with the same kinetic energy it had prior to the collision. l a b. recoils with a lower kinetic energy with the nucleus emitting a 4 gamma ray.

c. is absorbed by the nucleus, wi" the nucleus emitting a gamma ray.

d. recoils with a higher kinetic caergy, with the nucleus emitting a i gamma ray.

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QUESTION 002 (1.00)

An example of a fissile isotope which occurs naturally is:

a. Pu-239 1

l b. U-238

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c. U-235

d. Th-232  :

! OUESTION: 003 (1.00)

Given: Shutdown margin $4.50 1 Control Rod 1 $2.00 Control Rod 2 $2.00 Control Rod 3 $1.00 What is the excess reactivity for this reactor?

a. 50.50 1

b. $1.50

c. $2.50

d. $5.0C

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

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A.REACTORTHEORY.THER!dDYNAMICSA*CFACILITYOPERATINGCHARACTERISTICSPage4 OUESTION: 004 (1.00)

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.

QUESTION: 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 S,,f.

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.

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

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] A. REACTOR THEORY. THERM 0bYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 5 0UESTION: 007 (1.00)

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

a. Inserting an experiment which adds positive reactivity.

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

c. Depletion of burnable poison.

d. Depletion of uranium fuel, i OUESTION: 008 (1.00)

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

4 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 I

for the decay of Xe-135.

I 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 sudde ily removed from the reactor. The eK rr 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 THERMdbYNAMICS AND FACILITY OPERATING CHARACTERIS 0UESTION: 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.

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

c. the positive reactivity due to the fuel temperature increase i

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 thermal utilization factor is:

a. 0.47

b. 0.62

c. 0.67

d. 1.613

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

A. REACTOR THEORY. THERM 0' DYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 7 QUESTION: 012 (1.00)

Refer to the Regulating Rod Integral Rod Worth curve, attached. The regulating l rod is at position 625. A experiment with a reactivity worth of $0.60 is inserted into the reactor, and as a result the regulating rod moves into the core. The experiment has a reactivity worth of and the regulating rod is at position ,

a. + $0.60: 375

b. + $0.60: 405

c. - $0.60: 375

!l d. - $0.60: 405 i

OUESTION: 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 is 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 QUESTION: 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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A. REACTOR THEORY. THERM 0' DYNAMICS AND FACILITY OPERATING CHARACTERISTICSPage 8 l

OUESTION: 015 (1.00) i The Inhour Ecuation relates reactivity insertion, p. to reactor period. T.

Reactivity insertion A is +0.001 delta k/k. and reactivity insertion B is -0.001 delta k/k. The absolute value of the period will be:

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a. smaller for A. I

b. larger for A.

c. smaller for B.

d. the same for A and B.

QUESTION: 016 (1.00)

The reactor was pulsed on two successive occasions. On the second occasion, the peak power was four (4) times larger than on the first occasion. The reactivity inserted on the second occasion, as compared to the first, was approximately:

a. twice as much.

b. three times as much.

c. four times as much.

d. eight times as much.

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.REACTORTHEORY.THERMNYNAMICSANDFACILITYOPERATINGCHARACTERISTICSPage9 OUESTION: 018 (1.00)

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

a. 33 Br 87 - > 33Kr 83 8 86

b. asBr ' -> 33Kr

c. 33 Br'8 -> .gKr es 8 8

d. 33 Br' -> 36Kr '

OUESTION: 019 (1.00)

Reactor A increases power from 10% to 20% with a doubling time of 50 seconds.

Reactor B increases power from 20% to 30% with a doubling time 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.

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

B. NORMAL / EMERGENCY PROCLDURES & RADIOLOGICAL CONTROLS Page 10 QUESTION: 001 (1.00)

In accordance with Procedure No. 1. " Biennial Control Rod Inspection." the procedure is not considered to be complete unless:

a. a new integral rod worth curve is measured.

b. rod-drop time measurements from full withdrawal to full insertion are made.

c. a new differential rod worth curve is measured.

d. the reactivity insertion rate is measured.

QUESTION: 002 (1.00)

In accordance with the KSU Fitness-For -Duty Agreement, which ONE of the following statements is NOT true?

a. An arrest for possession or distribution of a controlled substance will result in the permanent loss of access to the Nuclear Reactor Facility.

b. Consumption of alcohol is prohibited for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> preceding any scheduled activity within the Facility.

c. Extended use of prescription or over-the-counter drugs is to be reported to the examining physician during employment physicals.

d. Consumption of alcohol during an abstinence period need not necessarily preclude an individual's responding to an emergency.

QUESTION: 003 (1.00)

An alpha particle assay of the primary coolant is to be performed. In accordance with Procedure No. 21. " Alpha-Particle Assay of Reactor Liquids." the purpose of this assay is to:

a. assure compliance with limits for alpha-particle activity in effluents to the sanitary sewer system.

b. detect the presence of uranium in the coolant due to clad leakage.

c. detect leakage from an in-core experiment.

d. detect the presence of N-16.

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

B. NORMAL /EMERGENCYPROGIDURES&RADIOLOGICALCONTROLS Page 11 OVESTION: 004 (1.00)

There has been a confirmed breach of cladding for multiple fuel elements. In accordance with the Emergency Plan, this event would be classified as a(n):

a. Unusual Event.

b. Alert.

c. Site Emergency.

d. General Emergency.

QUESTION: 005 (1.00)

In accordance with the Emergency Plan a Medical Incident is defined as:

a. a laboratory accident involving radiation exposure.

b. bodily injury requiring medical treatment.

c. a laboratory accident involving radiation exposure accompanied by bodily injury.

d. a laboratory accident involving radioactive contamination.

QUESTION: 006 (1.00)

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

a. The sum of the absolute reactivity worths of all experiments =

$2.20. I

b. A pulse reactivity insertion of $2.20.

c. A reactivity insertion rate of a standard contol rod = $0.87 per second.

d. Operating in steady state mode with the linear power channel inoperable.

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

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B. NORMAL / EMERGENCY PROGlDURES & RADIOLOGICAL CONTROLS Page 12 l l

QUESTION: 007 (1.00)

A group of five (5) visitors plus an escort is going to enter the reactor bay.

In accoraonce with Procedure No. 9. " Entrance to the Reactor Bay - Visitor Control." which ONE of the following is correct?

a. If the reactor is operating. each member of the group must have a TLD badge or pocket dosimeter.

b. If the reactor is operating, the group cannot enter the reactor bay without the approval of the Reactor Facility Director.

c. If the reactor is not operating, there must be at least two TLD badges or pocket dosimeters for the group.

d. If the reactor is not operating, the group may enter the reactor bay I with the permission of the Reactor Operator on duty at the console.

4 QUESTION: 008 (1.00)

The Total Effective Dose Equivalent (TEDE) is defined as the sum of the deer,-dose l equivalent and the committed effective dose equivalent. The deep-dose equi /aient i is related to:

a. the dose to organs or tissues.

b. the external exposure to the skin or an extremity.

c. the external exposure to the lens of the eye. l

d. the external whole-body exposure.

QUESTION: 009 (1.00)

I 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 linear power.

d. loss of high voltage.

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

B. NORMAL /EMERGENCYPR0dDURES&RADIOLOGICALCONTROLS Page 13 OUESTION: 010 (1.00)

In accordance with 10CFR55, a licensed operator must:

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

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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.

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d. notify the NRC within 30 days following an arrest.

OUESTION

011 (1.00)

} In accordance with the Technical Specifications, which ONE of the following i

conditions is NOT permissible when the reactor is operating, or about to be operated?

! a. Primary water temperature = 110 F.

b. Minimum shutdown margin - $0.87.

c. Maximum available reactivity above cold, clean condition - $2.20.

d. Pool water conductivity = 1.6 micromho/cm.

QUESTION: 012 (1.00)

The reactor facility must be evacuated due to high radiation readings as a result of an accident. Contaminated personnel will assemble at:

a. the lobby of Ward Hall.

b. the University Student Health Center.

c. the Ward Hall basement restroom area.

d. the North Hall Emergency Supplies area.

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

l l B. NORMAL /EMERGENCYPROGkDURES&RADIOLOGICALCONTROLS Page 14 I

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 effective dose equivalent of five (5) rems.

b. limits on the release of effluents to an 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: 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?

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a. 2

b. 6

c. 7

d. 10 QUESTION: 015 (1.00)

Which ONE of the folowing is expressly forbidden?

a. Mercury-glass thermometer in the reactor pool. I

b. Gasoline in the reactor bay.

c. Carbon tetrachloride in the reactor bay.

d. Acetone in the reactor bay.

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

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B.

NORMAL /EMERGENCYPR0(EDURES&RADIOLOGICALCONTROLS Page 15 0UESTION: 016 (1.00)

"During experiments involving the use of a standard TRIGA instrumented element in the central thimble of the core, the reactor shall not be operated in the pulse mode, or atgreater fuel temperature power than levels350 greater than 100 kW. or with a measured central C." This is an example of a:

a. safety limit.

b. limiting safety system setting.

c. limiting condition for operation.

d. surveillance requirement.

QUESTION: 017 (1.00)

In accordance Technicium-99 with is used as Procedure a source because: No. 8. " Calibration of Continuous Air Monitors a.

its decay particles and energies are similar to Ar-41.

b.

its decay particles and energies are similar to I-131.

c.

its half-life is long enough so that it does not decay appreciably.

d.

it produces count rates large enough to be measured.

QUESTION: 018 (1.00)

The specific goal of the ALARA program is to assure that actual exposures are no greater than 10% of the occupational limits and 50% of the public limits prescribed by 10CFR20. Accordingly, the annual occupational goal limit is less than _ TEDE and the public goal limit is less than TEDE.

a. 5 Rem: 50 mrem

b. 500 mrem: 100 mrem

c. 500 mrem; 50 mrem

d. 100 mrem: 25 mrem

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

l B. NORMAL / EMERGENCY PR0(EDURE5 & RADIOLOGICAL CONTROLS Page 15 0UESTION: 016 (1.00)

"During experiments involving the use of a standard TRIGA instrumented element in the central thimble of the core, the reactor shall not be operated in the pulse mode, or at power levels greater than 100 kW. or with a measured central fuel temperature greater than 350 C." This is an example of a:

a. safety limit.

b. limiting . safety system setting.

c. limiting condition for operation.

d. surveillance requirement.

QUESTION: 017 (1.00)

In accordance with Procedure No. 8. " Calibration of Continuous Air Monitors."

Technicium-99 is used as a source because:

a. its decay particles and energies are similar to Ar-41.

b. its decay particles and energies are similar to I-131.

c. its half-life is long enough so that it does not decay appreciably,

d. it produces count rates large enough to be measured.

QUESTION: 018 (1.00)

The specific goal of the ALARA program is to assure that actual exposures are no greater than 10% of the occupational limits and 50% of the public limits prescribed by 10CFR20. Accordingly, the annual occupational goal limit is less than TEDE and the public goal limit is less than TEDE.

a. 5 Rem; 50 mrem

b. 500 mrem; 100 mrem

c. 500 mrem: 50 mrem

d. 100 mrem; 25 mrem

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

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C. PLANT AND RADIATION H'ONITORING SYSTEMS Page 16 0UESTION: 001 (1.00)

The water monitor vessel contains: l l

a. a Geiger-Mueller tube, a conductivity probe and a temperature probe. I

b. a flow meter, a Geiger-Mueller tube and a conductivity probe.

c. a resistivity probe, a temperature probe and a Geiger-Mueller tube.

d. a flow meter. a conductivity probe and a temperature probe.

QUESTION: 002 (1.00)

When the mode switch is placed in the "AUT0" mode:

a. the period scram is bypassed.

b. the regulating rod moves in response to the linear channel voltage.

c. the regulating rod moves in response to the percent power channel voltage.

d. the regulating rod will not fall into the core following a scram.

QUESTION: 003 (1.00)

The reactor is in the " PULSE" mode when the " air" switch 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.

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

A 9 4 C. PLANTANDRADIATIONMbNITORINGSYSTEMS Page 17

OUESTION

004 (1.00)

In the reactor cooling system, there is a pressure gauge on each side of the filter. The purpose of these gauges is to:

a. provide a differential pressure to measure flow through the deionizer.

b. provide a computer input for measuring system pressure.

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c. measure primary pressure to ensure that it is always lower than secondary pressure. i I

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d. measure the pressure drop across the filter to determine filter i

clogging.

, QUESTION: 005 (2.00)

Select from column B the actual rod movement that WoJld result from attempting to simultaneously move the combination of rods in column A. (Items in column 8 may be used once, more than once or not at all. Only one answer may be used for each item in column A.)

Column A Column B Attempted Rod Move Resulting Rod Movement

a. Pulse mode is engaged and 1. Shim rod moves up attempt to withdraw reg rod

2. Reg rod moves up

b. Attempt to withdraw shim and 3. Shim and reg rods reg rods (steady state mode) move up

c. Attempt to withdraw pulse and 4. Pulse rod moves up reg rod (steady state mode)

5. No rod motion

d. Shim rod is up 250 units, switch to pulse mode and attempt to raise pulse rod

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

C. PLANTANDRADIATIONIbNITORINGSYSTEMS Page 18 OUESTION: 006 (1.00)

In accordance with Procedure No. 16. "TRIGA MkII Reactor Shutdown." the reactor 4

can be shut down using an intentional safety system scram. This is accomplished

, by:

a. driving the control rods to their down positions and actuating the

, manual scram bar.

i

b. actuating the manual scram bar.

c. raising reactor power to the 104% scram setpoint.

d. manually adjusting a scram setpoint until a scram condition is reached.

QUESTION: 007 (1.00) 4 When the percent power channel is used for neutron detection, how is the gamma j flux accounted for?

a. Pulse height discrimination is used to eliminate the gamma flux.

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

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c. The gamma flux is cancelled by creating an equal and opposite gamma current in the detector.

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

QUESTION: 008 (1.00)

The MIII fuel elements:

a. are about 20% enriched uranium with stainless steel clad and samarium burnable poison.

b. are about 38% enriched uranium with stainless steel clad and no burnable poison.

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

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

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

C. PLANT AND RADIATION tibNITORING SYSTEMS Page 19 l

OUESTION: 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 timer setting that vents the pneumatic piston. I

b. The ,)ressure of the air applied to the pneumatic piston.

c. The position of the shock absorber.

d. The reactivity of the reactor prior to firing the pulse.

QUESTION: 010 (1.00) l The purpose of the diffuser above the core during operation is to:

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

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.

QUESU QJ: 011 (1.00)

The shim rod and the regulating rod are constructed of:

a. graphite with aluminum cladding.

b. boron and carbon with aluminum cladding.

c. boron and carbon with stainless steel cladding.

d. graphite and boron with aluminum cladding.

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

9 C. PLANTANDRADIATION60NITORINGSY3TEMS Page 20 QUESTION: 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 Wide Range Channel 1. Compensated Ion Chamber

b. Multi-Range Linear Channel 2. Uncompensated Ion Chamber

c. Percent Power Channel 3. Fission Chamber

d. Pulse Channel 4. G-M Tube i

OUESTION: 013 (1.00) l' The central thimble is an aluminum tube extending from the top of the reactor tank and terminating:

a. below the bottom grid plate.

t at the bottom grid plate.

2 b.

c. at the midpoint of the core.

d. at the top grid plate.

QUESTION: 014 (1.00)

Which ONE of the following describes the action of the rod control system to l drive the magnet draw +ube down after a dropped rod?

a. Deenergizing the rod magnet initiates the down motion of the draw tube.

b. MAGNET DOWN limit switch initiates the down motion of the draw tube.

c. R0D DOWN limit switch initiates the down motion of the draw tube.

d. Deenergized contact light (DS317) and MAGNET UP limit switch initiate the down motion of the draw tube.

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

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

J C. PLANTANDRADIATIONKbNITORINGSYSTEMS Page 21 QUESTION: 015 (1.00) 1 Coolant flow in the de.mineralizer loop of the reactor coolant system is measured by:

a. differential pressure across the filter.

4

b. a flow meter at the outlet of the demineralizer.

i

c. an orifice at the inlet to the heat exchanger.

d. a flowmeter at the inlet of the primary pump.

OUESTION 016 (1.00)

Which ONE of the following statements correctly describes the purpose of the potentiometer in the control rod drive assembly.

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

b. Prov' _ variable voltage to the rod drive motor for regui cing control rod speed.

c. Provides potential voltage as required for resetting the electromagnet current.

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

QUESTION: 017 (1.00)

When the amber light on the control console associated with the pulse rod is extinguished, this indicates that:

a. the solenoid valve has been de-energized.

b. the shock absorber is located at its highest position.

c. the variable timer has timed out.

d. the air supply pressure is above 45 psig.

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

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

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

A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS l

ANSWER: 001 (1.00) I B.  !

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

l ANSWER: 002 (1.00)

C.

REFERENCE:

i

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

ANSWER: 003 (1.00) j A.

REFERENCE:

R. R. Burn. Introduction to Nuclear Reactor Operations, pg. 6-3.

ANSWER: 004 (1.00)

C. i i

REFERENCE:

R. R. Burn, Introduction to Nuclear Reactor Operations, pg. 4-8.  ;

ANSWER: 005 (1.00) l A. I

REFERENCE:

R. R. Burn. Introduction to Nuclear Reactor Operations, pg. 4-3. '

ANSWER: 006 (1.00)

A.

REFERENCE:

Glasstone, Sesonske. Nuclear Reactor Engineering. 3rd. Edition, pg.154.

The volume of the sphere is larger than the volume of the cube, and its ratio of surface area to volume is smaller.

ANSWER: 007 (1.00) ,

D.

REFERENCE:

Anything which adds negative reactivity increases the shutdown margin.

I ANSWER: 008 (1.00)

B.

REFERENCE:

R. R. Burn, Introduction to Nuclear Reactor Operations, pg. 8-10.

ANSWER: 009 (1.00)

C.

REFERENCE:

R. R. Burn. Introduction to Nuclear Reactor Operations, pg. 4-1.

ANSWER: 010 (1.00)

A.

REFERENCE:

Since t;te fuel temperature must drop. positive reactivity is added.

! ANSWER: 011 (2.00) y C. l

REFERENCE:

R. R. Burn. Introduction to Nuclear Reactor Operations, pg. 3-15. i

! A total of 70 thermal neutrons (100-20-10) are absorbed in fuel plus other j materials. Since the reactor is critical, there were 40 fissions (40x2.5 - 100).

i Since 85% of absorptions result in fission, there were 40/0.85 - 47 neutrons absorbed in fuel. The thermal utilization - 47/70 = 0.67.

ANSWER: 012 (1.00) i A.

REFERENCE:

See attached integral rod worth curve.

ANSWER: 013 (1.00)

C.

1

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. l

REFERENCE:

l R. R. Burn Introduction to Nuclear Reactor Ooerations pg. 2-51.

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

ANSWER: 015 (1.00)

A.

REFERENCE:

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

ANSWER: 016 (1.00)

A.

REFERENCE:

KSU Operations Manual, pg. C4-3.

ANSWER: 017 (1.00)

B.

REFERENCE:

Procedure No. 2. Annual Power Level Calibration.

ANSWER: 018 (1.00)

D.

REFERENCE:

Lamarsh. Introduction to Nuclear Engineering, 2nd Edition. pg.19.

ANSWER: 019 (1.00)

D.

REFERENCE:

The power for reactor A increases by a factor of 2, while the power for reactor B increases by a fcctor of 1.5. Since the periods are the same, power increase B takes a shorter time.

9 i ., l B. NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS i ANSWER: 001 (1.00)

B.

REFERENCE:

i Procedure No. 1. Biennial Control Rod Inspection, pg.3.

ANSWER: 002 (1.00)

A.

REFERENCE:

Procedure No. 9. Appendix. Fitness-For ' y &"eement.

ANSWER: 003 (1.00)

A.

REFERENCE:

Procedure No 21. Alpna-Particle Assay of Reactor Liquids, pg. 1. l ANSWER: 004 (1.00)

B.

REFERENCE:

KSU Operations Manual, pg. A4-10.

ANSWER: 005 (1.00)

C.

REFERENCE:

KSU Operations Manual. pg. A4-5.

ANSWER: 006 (1.00)

B.

REFERENCE:

KSU Technical Specifications. Section E.4.

ANSWER: 007 (1.00)

A.C.

REFERENCE:

Procedure No. 9. Entrance to the Reactor Bay - Visitor Control pg.1.

ANSWER: 008 (1.00)

D.

REFERENCE:

KSU Operations Manual, pg. B1-5.

ANSWER: 009 (1.00)

A.

REFERENCE:

KSU Operations Manual. pg. Al-16.

ANSWER: 010 (1.00)

A.

REFERENCE:

KSU Operations Manual, pg. B4-2. 10CFR55.59(a)(2).

1 I " '

ANSWER: 011 (1.00) +

B.

REFERENCE:

1 i KSU Technical Specifications Section E.5.

ANSWER: 012 (1.00) I C.

REFERENCE:

KSU Operations Manual, pg. A4-6.

ANSWER: 013 (1.00)

D. ,

REFERENCE:

KSU Operations Manual, pg. B1-6.

$ ANSWER: 014 (1.00)

C.

REFERENCE:

!' KSU Operations Manual, pg. F9-3.

Each sheet of lead reduces the exposure rate by half. First sheet - 50%; second

sheet - 25%

third sheet - 12.5%, etc.

ANSWER: 015 (1.00)

A. J

REFERENCE:

KSU Operations Manual. pg. A2-5.

2 ANSWER: 016 (1.00)

C.

REFERENCE:

KSU Operations Manual, pg. B5-1.

ANSWER: 017 (1.00)

B.

REFERENCE:

Procedure No. 8. Calibration of Continuous Air monitors, pg. 3.

1 ANSWER: 018 (1.00)

C.

REFERENCE:

KSU Operations Manual, pg. B1-3.

l -

C. PLANT AND RADIATION WDNITORING SYSTEMS ANSWER: 001 (1.00)

A.

REFERENCE:

KSU Operations Manual, pg. Al-10.

ANSWER: 002 (1.00)

B.

REFERENCE:

Procedure NO. 23. Automatic Flux Control System, pg. 1.

ANSWER: 003 (1.00)

C.

REFERENCE:

KSU Operations Manual, pg. Al-18.

ANSWER: 004 (1.00)

D.

REFERENCE:

KSU Operations Manual, pg. Al-11.

ANSWER: 005 (2.00)

A.5: B.5: C.4; D.5

REFERENCE:

Procedure No. 5. Semi-Annual Check of Minimum Interlocks, pg.1 ANSWER: 006 (1.00)

D.

REFERENCE:

Procedure No. 16. TRIGA MkII Reactor Shutdown.

ANSWER: 007 (1.00)

B.

REFERENCE:

KSU Operations Manual, pg. Al-15.

ANSWER: 008 (1.00)

D.

REFERENCE:

KSU Operations Manual pg. Al-4.

ANSWER: 009 (1.00)

C.

REFEREACE:

Experiment No. 23. Pulsed Operation.

ANSWER: 010 (1.00)

A.

REFERENCE:

I ANSWER: Ol' (1.00) v' B.D. ,

REFERENCE:

l KSV Operations Manual, pg. Al-6.

ANSWER: 012 (2.00)

A.3: B.1: C.2: D.2 l i

REFERENCE:

KSU Operations Manual, pg. Al-12.

ANSWER: 013 (1.00)

A. ,

REFERENCE:

i KSU Operations Manual, pg. Al-7.

ANSWER: 014 (1.00)

C.

REFERENCE:

KSU Operations Manual, pg. Al-17.  ;

ANSWER: 015 (1.00)

B.

REFERENCE:

KSU Operations Manual, pg. Al-10.

ANSWER: 016 (1.00)

A.

REFERENCE:

KSU Operations Manual, pg. Al-16.

ANSWER: 017 (1.00)

D.

REFERENCE:

KSU Operations Manual, pg. Al-18.

l A. REACTOR THEORY THERW) DYNAMICS 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 4

003 a b c d 4

004 a b c d '

005 a b c d 006 a b c d l 007 a b c d j 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 i 014 a b c d 1 015 a b c d 016 a b c d i

017 a b c d 018 a b c d

019 a b c d

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

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B. NORMAL /EMERGENCYPROCEdURES&RADIOLOGICALCONTROLS ANSWER SHEET  !

MULTIPLE CHOICE (Circle or X your choice)

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

l 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 l

l l

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

l l

. 1 C. PLANTANDRADIATION#dNITORINGSYSTEMS 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 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

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

e v' EQUATION SHEET l

0 = m c, AT CR i (1-Keff)3 - CR2 (1-Keff}2 I SUR = 26.06/r P = P 10*"

o P = Po e(*

• r = (t*/p) + [(S-p)/A,ffp]

A,rr = 0.1 seconds ~' DR11 0 2 - DR 22 D2  ;

DR = DRo e"t DR = 6CiE/02 1

p = (Keff-1)/Keff 1 eV = 1.6x10'" watt-sec. l 1 Curie = 3.7x10" dps 1 gallon water = 8.34 pounds .

1 1 Btu = 778 ft-lbf F = 9/5 C + 32 1 He = 3.41x106BTU /hr C = 5/9 ( F - 32)

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