ML20128F612

Initial Exam Rept 50-116/OL-96-02 Conducted During Wk of 960923.Exam Results:Sro Applicant Did Not Pass Exam

ML20128F612
Person / Time
Site:	University of Iowa
Issue date:	10/01/1996
From:	Eresian W NRC (Affiliation Not Assigned)
To:
Shared Package
ML20128F595	List: ML20128F591 ML20128F612
References
50-116-OL-96-02, 50-116-OL-96-2, NUDOCS 9610080141
Download: ML20128F612 (34)

Text

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i U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT N0.: 50-116/0L-96-02 FACILITY DOCKET NO.: 50-116 FACILITY LICENSE NO.: R-59 FACILITY: Iowa State University EXAMINATION DATES: September 26, 1996 EXAMINER: Warren J. Eresi , Chief Examiner SUBMITTED BY: RAA.A., /%

Warren J. Ertsian, Chief Eximiner

/c Date

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SUMMARY

The NRC administered an initial license examination to one Senior Reactor Operator (Instant) applicant. The applicant did not pass the examination.

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ATTACHMENT 1 4

9610080141 961002 PDR ADOCK 05000116 V PDR

REPORT DETAILS

1. Examiners:  !

Warren J. Eresian, Chief Examiner

2. Results:

R0 SRO Total '

(Pass / Fail) (Pass / Fail) (Pass / Fail)

NRC Grading: 0/1 0/1

3. Written Examination:

The applicant failed Category A of the written examination, but passed the examination overall.

4. Operating Test:

The applicant passed the operating test.

5. Exit Meeting:

An exit meeting was held on September 25, 1996. Present were:

Warren J. Eresian, NRC Chief Examiner Mr. Scott Wendt, Reactor Supervisor The NRC thanked the Iowa 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 p t

FACILITY: Iowa State University REACTOR TYPE: UTR-10 DATE ADMINISTERED: 09/26/96 REGION: 3 l CANDIDATE:

! INSTRUCTIONS TO CANDIDATE:

l l 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 l-category is required to pass-the examin3 tion.

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

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20 A. REACTOR THEORY.

THERMODYNAMICS AND FACILITY l DPERATING CHARACTERISTICS 17 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND l

RADIOLOGICAL CONTROLS  ;

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, 18 C. PLANT AND RADIATION l MONITORING SYSTEMS l 55  %

FINAL GRADE  !

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

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Candidate's Signature

_ . . _ . - e-r ___ _ _ . ~ , . ,_._.._,y _--.-7 y y-r

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

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

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

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 l even the appearance or possibility of cheating. j

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. Wnen 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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l, A. REACTOR THEORY THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 3 i i 1 i OVESTION: 001 (1.00) i Inelastic Scatterina is the process whereby a neutron collides with a nucleus and: j l a. recoils with the same kinetic energy it had prior to the collision.  !

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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 gamma ray,

d. re a is with a higher kinetic energy, with the nucleus emitting a gamma ray.

QUESTION 002 (1.00)

An example of a fissile isotope which occurs naturally is:

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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 What is the excess reactivity for this reactor?

a. $0.30

b. $1.50

c. $2.50

d. $5.00 l

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

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l-i A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 4 l i

OUESTION: 004 (1.00) i During the time when reactor power decreases. the delayed neutron fraction. B:

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.

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

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d. remains unchanged. '

QUESTION: 005 (1.00) l When a reactor is oromot critical, the neutron multiplication rate is determined by: j

a. the generation time of prompt neutrons only. j

b. the value of B,rr.  !

c. the generation time of delayed neutrons only. '

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

l QUESTION: 006 (1.00)

The core of reactor A is in the form of a s)here of radius R. The core of reactor B is in the form of a cube, with edge length 1. The neutron leakage from reactor B. l compared to reactor A will be: j

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 *****)

I i l A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 5 l OUESTION: 007 (1.00) l t'hich ONE of the following conditions would INCREASE the shutdown margin of a reactor?  !

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a. Inserting an experiment which adds positive reactivity.  !

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

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c. Depletion of burnable poison.

d. Depletion of uranium fuel.

QUESTION: 008 (1.00) i A compensated ion chamber is used to monitor reactor power. Which ONE of the following describes the response of the meter indication following a reactor scram if the CIC is overcompensated? -

a. Indicated neutron flux will be HIGHER than actual neutron flux.

b. Indicated neutron flux will be LOWER than actual neutron flux,

c. Indicated neutron flux will be the SAME as actual neutron flux.  :

d. Indicated neutron flux will be either HIGHER or LOWER than actual ,

neutron flux, depending on reactor power.

-QUESTION: 009 (1.00)

A reactor is operating at criticality. Instantaneously, all of the delayed neutrons are suddenly removed from the reactor. The K,,, 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 CHARACTERISTICS Page 6 QUESTION: 010 (1.00) l A reactor is critical at full rated pcwer, 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.

l 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 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 ca)tured in resonance core after they have reacled thermal energy.The peaks, and 10 remaining leak out neutrons areof the 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 *****)

! e A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 7 QUESTION: 012 (1.00) l Refer to the Regulating Rod Integral Rod Worth curve, attached. The regulating rod is at the 74% position. An experiment witti a reactivity worth of $0.13 is inserted into the reactor. and as a result the regulating rod moves into the core. The experiment has a reactivity worth of ind the regulating rod is at l

position .

a. + $0.13; 24

b. + $0.13: 51

c. - $0.13: 24

d. - 50.13: 51 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 l

d. 0.0140 l i

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. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 8 QUESTION: 015 (1.00)

The Inhour Eauation 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 vatus of the period will be:

a. smaller for A.

b. larger for A.

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! c. smaller for B.

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d. the same for A and B.

QUESTION: 016 (1.00)-

A fuel element' loading and approach to critical is monitored using a 1/M plot.

After a few fuel elements are loaded, the count rate existing at that time is selected to become the new initial count rate (R,). More fuel elements are added As a result of re and the approach to criticality proceeds. initial count rate with the new one, criticality will

a. sooner (fewer fuel elements loaded).

b. later (more fuel elements loaded).

c. with the same number of fuel elements loaded.

d. sooner, later or the same, depending on the ratio between the original initial count rate and the new initial count rate.

QUESTION: 017 (1.00)

The equations which describe the UTR-10 startup neutron source are:

a. Pu-239 alpha + U-235 Be-9 + alpha -> C-12 + neutron

b. Pu-239 -> alpha + U-235 B-10 + alpha -> N-13 + neutron

c. Pu-239 -> beta + U-239 Be-9 + beta -> Li-8 + neutron

d. Pu-239 -> beta + U-239 B-10 + beta -> Be-9 + neutron

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

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1 A. REACTOR THEORY. THERMODYNAMICS AND FAClLITY OPERATING CHARACTERISTICS Page 9 QUESTION: 018 (1 00)

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

a. 3s Br 87 -> 33K r 83 87 86

b. asBr - > 3sKr l 87 86

c. 3 sbr -> 3Kr )

87 87

d. 3 sbr - > 3sKr OVESTION: 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. l l

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 dose rate 10 feet from a )oint source is 25 mr/hr. An o)erator needs to work on instrumentation 3 feet from tie source. If the operator worcs for 1 and 1/2 hours at 3 feet from the source. he will receive a dose of:

a. 83 mrem.

b. 125 mrem.

c. 278 mrem.

d. 417 mrem.

QUESTION: 002 (1.00)  ;

During power operation, the reactor o)erator notices that reactor plant power has l exceeded 15 kW. In accordance with t1e Technical Specifications, the reactor operator must:

a. Level reactor power and contact the .NRC.

b. Shutdown the reactor and contact the reactor manager.

c. Shut down the reactor and write a written report of the occurrence to the NRC.

d. Reduce reactor power to 1 watt and contact the NRC.

1 OVESTION: 003 (1.00) i l

l Shutdown margin is required to be measured:

a. semi-annually.

b. daily during power operations.

c. weekly, if control rods have not moved far the past 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.

d. following refueling.

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

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-B. -NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 11 l

l OVESTION: 004 (1.00) l In order to move fuel, the moderator must be:

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a. drained out and the control rods removed. i i

b. drained out and the control rods inserted.

c. full and the control rods removed. l l

d. full and the control rods inserted. l l

l QUESTION: 005 (1.00) l How is " confinement" verified?

a. Place the confinement at 2 psi above atmospheric pressure.

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b. Check that roof-level windows can be closed in less than two minutes.

c. Check for normal closure on confinement windows and experiment covers at least once per quarter,

d. Check for normal closure on confinement doors and windows at least once per quarter.

QUESTION: 006 (1.00)

The reactor is ready for start-up and it has been 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> since the last

)recritical check. Primary coolant outlet temperature has increased 5 degrees F.

Prior to start-up:

a. a short-form precritical checklist is required.

b. a short-form precritical checklist including NI calibrations is required.

c. a (standard) precritical checklist is required.

d. a (standard) precritical checklist without the NI calibrations and radiation monitor checks is required.

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

B. NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 12 i 2

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. QUESTION: 007 (1.00) '

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! Reactor power is 1.0 Watt with the control system in Aut miatic. The position of the 5 regulating rod is unknown. The reactor operator must:

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l j a. scram the reactor.  !

i t j b. select Manual control mode.  !

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l c. put the reactor in hot standby.  :

I d. drive the regulating rod until it can be found.  :

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I I OUESTION: 008 (1.00) J

1 An announcement has been made that the building is to be evacuated. The SR0 has directed you to " secure the reactor." This is done by:

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a. Securing the primary coolant pumps, j

b. Initiating building confinement.

c. Opening the moderator dump valve.

d. Initicting a scram by removing the key.

QUESTION: 009 (1.00)

An area radiation monitor is reading 55 mrem /hr and the alarm is in. A portable monitor reading is taken ands reads 60 mrem /hr. An operator must:

a. Place the reactor in hot standby and initiate evacuation,

b. Shutdown the reactor and monitor all other area radiation monitors,

c. Manually scram the reactor and initiate evacuation.

d. -Determine location and magnitude of reading (s) and shutdown the reactor.

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

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, B. NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS Page 13 ,

i OUESTION: 010 (1.00)

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An evacuation has been initiated. You are in class on campus, and all off duty operators have been directed to report to the Emergency Support Center. You would i

report to the

!; a. Environmental Health and Safety office. l.

I b. Basement room (Room 9) in Sweeney Hall.  !

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c. Student Health Center, j l

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d. Security office.

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! OUESTION: 011 (1.00)

! Two reactor parameters which are protected by Safety Limits are:

j a. fuel element temperature and primary coolant flow rate. l j b. steady state power level and primary coolant flow rate.

c. moderator level and primary coolant outlet temperature.

d. moderator level and steady state power level.

, OUESTION: 012 (1.00) f

, In accordance with 10 CFR 20. the " Derived Air Concentration (DAC)" refers to:

i 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 2 dose equivalent of five (5) rems.

1 i b. the concentration of a given radionuclide in air which, if breathed for a working year of 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 j equivalent of 5 rems.

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

d. limits on the release of effluents to an unrestricted environment.

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

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

Which ONE of the operations below requires the presence of a health physics- i qualified individual?  ;

a. Calibration of area radiation monitors.  :

b. Fuel transfer operation.  !

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c. Any maintenance activity involving the reactor safety system which could  !

cause a significant increase in reactivity. t

d. Relocation of any in-core experiment with a reactivity worth greater  ;

than 0.14% delta k/k.

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QUESTION: 014 (1.00)

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"The primary coolant temperature, flow rate. conductivity and radiation level at the deionizer shall be measured and recorded at startup and at least every four hours l when the reactor is operating " This is an example of a(n): )

a. safety limit.

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b. limiting safety system setting.  ;

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c. limiting condition for operation.

d. surveillance requirement.

QUESTION: 015 (1.00)

Which ONE of the operations below does NOT requirr the direction of a Senior Reactor Oparator?

a. Recovery from an unplanned shutdown.

b. Fuel transfer operation,

c. Any maintenance activity involving the reactor safety system which could cause a significant increase in reactivity.

d. Relocation of any in-core experiment with a reactivity worth of 0.14% .

delta k/k. j i

(***** CATEGORY B CONTINUED ON NEXT PAGE *****) i 1

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B. NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CCNTROLS Page 15 OVESTION: 016 (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 )ower meter to correspond to the heat Jalance. i

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

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

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2 C. FACILITY AND RADIATION MONITORING SYSTEMS Page 16 .

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OUESTION: 001 (1.00) i The shim-safety and the regulating rods have "up" and "down" pushbutton switches for '

controlling rod motion. Which ONE of the following describes the res onse of the >

i shim-safety and regulating rods to the operation of these pushbuttons l 4 i

a. When the shim-safety and the regulating rod "up" pushbuttons are l l simultaneously depressed, both rods will be simultaneously withdrawn.  ;

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i b. When the shim-safety and the regulating rod "up" pushbuttons are l i simultaneously depressed. the shim-safety is withdrawn to full out and f then the regulating rod will be withdrawn.

c. When the shim safety and the regulating rod "down" pushbuttons are simultaneously depressed, both rods will be simultaneously inserted.

i d. When the shim-safety and the regulating rod "down" pushbuttons are

simultaneously de ressed, the shim-safety will be inserted to full in and then the regu ating rod will be inserted.

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- OUESTION

002 (1.00) i Which DNE of the following is the PRINCIPAL purpose for maintaining the primary f deionizer in service during reactor power operations exceeding 7 days?

a. To maintain conductivity below 2 micrombos/cm and to remove the soluble aluminum hydroxide corrosion products from the primary coolant.

! b. To maintain conductivity below 10 micrombos/cm and to remove the soluble i aluminum hydroxide corrosion products from the primary coolant.

{ c. To maintain conductivity below 2 micrombos/cm to prevent the excessive 1 loss of fuel cladding thickness due to corrosion.

! d. To maintain conductivity below 10 micrombos/cm to prevent the excessive loss of fuel cladding thickness due to corrosion.

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

C. FACILITY AND RADIATION MONITORING SYSTEMS Page 17 {

QUESTION: 003 (1.00) l Which ONE of the following describes the panel indicating light response to the position of the dump valve? j I

a. The light comes ON when the dump valve is FULLY CLOSED, and the light goes 0FF when the valve reaches the FULLY OPEN position. l

b. The light goes 0FF when the dump valve is FULLY CLOSED and the light comes ON when the valve reaches the PARTIALLY OPEN position.  ;

c. The light comes ON when the dum) valve is FULLY OPEN, and the light goes -

0FF when the valve reaches the ULLY CLOSED position.

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d. The light goes 0FF when the dump valve is FULLY OPEN, and the light i comes ON when the valve reaches the PARTIALLY CLOSED position.

I OUESTION: 004 (1.00)  ;

The reactor is operating at 10 kW when the dump tank develops a small leak. The  :

leak can be detected because:

a. periodic measurements of the primary coolant volume will discover the leak.

b. there will be disruptions and/or reductions in primary coolant flow rate j due to the leak.

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c. power will decrease as reactor core tank water is lost due to the dump tank leak.

d. the dump valve will automatically open to restore dump tank water level because of the leak.

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

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l. i C. FACILITY AND RADIATION MONITORING SYSTEMS Page 18 :

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OUESTION: 005 (1.00)

A level of 49.5 inches was selected as the normal operating core tank water level because it: i

a. provides the maximum shielding for controlling radiation levels in areas  ;

outside the reactor.

b. ensures the nuclear instrumentation detectors are measuring an accurate _

reactor neutron flux. '

, i l c. ensures an adequate net positive suction head for the Primary l Circulating Pump.

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d. provides the design amount of negative reactivity for insertion when the l dump valve is opened.  ;

1 OVESTION: 006 (1.00) ,

, While withdrawing control rods, the coolant outlet temperature exceeds 160 degrees l F. As a result:

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a. the reactor scrams.

b. a control rod interlock occurs. ,

c. the automatic dump valve opens.

d. an alarm occurs.

QUESTION: 007 (1.00)

A loss of normal A/C power has occurred, and the Standby A/C system is supplying power. What is the ULTIMATE power source to the facility alarms?

a. A charger transfer unit.

b. An inverter.

c. 120 volt A/C from the standby generator.

d. A lead-calcium battery.

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

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l C. FAClLITY AND RADIATION MONITORING SYSTEMS Page 19 OUESTION: 008 (1.00)

The moderator dump system functions to shut down the reactor by:

a. increasing neutron leakage.

b. decreasing neutron leakage.

c. increasing neutron reflection.

d. decreasing neutron slowing down time QUESTION: 009 (1.00)

Reactor power is stable at 10 mW when a sudden increase is noticed in reactor power.

The increase is due to:

a. the regulating rod moving inward.

b. moderator temperature suddenly increasing.

c. core tank level suddenly decreasing.

d. the source being inserted into the core.

QUESTION: 010 (1.00)

Which ONE of the following conditions will cause a reactor scram?

a. Reactor power is 12 kW.

b. Reactor period is 4.5 seconds.

c. Closures are open; reactor power " I mW.

d. Moderator level is 40 inches.

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

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C. FACILITY AND RADIATION MONITORING SYSTEMS Page 20 QUESTION: 011 (1.00)

Which ONE of the following scram setpoints utilizes a one-out-of-two logic.  !

a. Thermal column open.  !

. b. Moderator level greater than 55 inches I

c. Period less than 10 seconds and greater than 5 seconds

d. Period less than 5 seconds

'OUESTION: 012 -(1.00)

The overflow pipe in each of the reactor core tanks directs the coolant overflow to the:

a. dump tank,

b. shield tank,

c. inlet to the primary coolant pump.

d. inlet to the deionizer.

I OUESTION: 013 (1.00)

. Dump tank temperature control is maintained by a locally mounted controller. In order to avoid the design temperature limit of 180 degrees F., temperature is measured at the: )

a. primary coolant inlet to the dump tank

b. primary coolant outlet of the dump tank.

c. dump tank surface.

d. primary coolant outlet from the reactor core tanks.

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

j C. FACILITY AND RADIATION MONITORING SYSTEMS Page 21 i

OVESTION: 014 (1.00)  !

Which ONE of the following describes operation in the Automatic mode:

a. The output from the fission chamber is compared to the demand from the power regulator,

b. The period signal from the compensated ion chamber limits the rate of  !

power increase. j

c. The output from the compensated ion chamber is compared to the demand from the power regulator.  ;

d. The output from the linear power channel is compared to the demand from the power regulator. ,

OUESTION: 015 (1.00)

The reactor is in the Automatic mode at a power level of 5 kW. The neutron detector from which the control system receives its input fails low (signal suddenly goes to zero). As a result:

a. the control system inserts the regulating blade to reduce power to try to match the power of the failed detector.

b. the control system withdraws the regulating blade to increase power to try to meet the demand of the power regulator. '

c. the control system drops out of the Automatic mode into the steady-state manual mode, e d. the reactor scrams.

QUESTION: 016 (1.00)

Which ONE of the following correctly describes the purpose of the potentiometer in the shim-safety rod drive assembly?

a. Provides rod position indication.

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

c. Provides voltage for energizing the electromagnetic clutch.

d. Provides the voltage for energizing the limit switches.

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

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

i C. FACILITY AND RADIATION MONITORING SYSTEMS Page 22 QUESTION: 017 (1.00)

The reactor operator is following the startup procedure. When he attempts to withdraw control rods, the rods will not move. This occurs because:

a. the coolant pump motor circuit breaker is open.

b. the count rate setpoint has not been satisfied.

c. the moderator temperature setpoint has not been satisfied.  ;

d. automatic control has been selected. l OUESTION: 018 (1.00)  !

The level in the dump tank is decreasing slowly and the suction head to the primary  !

pump has decreased. These results indicate that:  ;

a. a reactor scram has occurred,

b. there is a leak in the secondary side of the heat exchanger. j

c. there is a leak in the primary side of the heat exchanger.

d. there is leakage past the dump valve.

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

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

l

I s I A. REACTOR THE0RY. THERMODYNAMICS'AND FACILITY OPERATING CHARACTERISTICS ANSWER: 001 '(1.00) ]

, B. '

REFERENCE:

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

1 ANSWER: 002 (1.00)

C. i REFERENCE-Lamarsh. Introduction to Nuclear Engineering. 2nd Edition, pg.104. ]

1 ANSWER: 003 (1.00)

A.  !

REFERENCE:

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

l

' ANSWER: 004 (1.00) i C.

REFERENCE:

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

ANSWER: 005 (1.00) l A. i l

REFERENCE:

R. R. Burn. Introduction to Nuclear Reactor Operations, pg. 4-3. j ANSWER: 006 (1.00)

A.

REFERENCE:

Glasstone. Sesonske. Nuclear Reactor Engineering. 3rd. Edition, pg. 154. i The volume of the sphere is larger than the volume of the cube, and its ration of l surface area to volume is smaller.

ANSWER: 007 (1.00) i D.

REFERENCE:

Anything which adds negative reactivity increases the shutdown margin.

ANSWER: 008 (1.00)

B.

REFERENCE:

Reactor Operations Training Projects, pgs. 27-28.

ANSWER: 009 (1.00)

C.

REFERENCE:

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

ANSWER: 010 (1.00)

.A.

REFERENCE:

Since the fuel temperature must drop. positive reactivity is added.

1

ANSWER: 011 (2.00) -

C.

REFERENCE:

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

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

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)

A.

REFERENCE:

See attached integral rod worth curve.

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. g. Burn. Introduction to Nuclear Reactor 0gerations 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)

C.

REFERENCE:

Reactor Operations Training Projects, pgs. 38-40.

ANSWER: 017 (1.00)

A.

REFIRENCE:

Fac lity Information, pg.16.

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 factor of 1.5. Since the periods are the same, power increase B takes a shorter time.

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

D.  !

REFERENCE:

(25 mrem /hr)(10 ft)^2 = (DR2)(3 ft)^2: (25)(100)/9 - 278 mrem /hr:

(1.5 hr)(278 mrem /hr) - 417 mrem  !

Training Manual for Reactor Operators, Vol. II. Radiological Safety. l A':SWER: 002 (1.00) .

B.

REFERENCE:

150 Technical Specifiations. Sect. 6.5.1 l ANSWER: 003 (1.00)  !

D. ,

REFERENCE:

ISU Technical Specifications Sect. 4.1.3 i ANSWER: 004 (1.00)

B. i

REFERENCE:

i'

-ISU Operations Procedure- Fuel Transfer C.4.

ANSWER: 005 (1.00)

D.  !

REFERENCE:

ISU Technical Specifications. Sect. 4.4.3 4 ANSWER: 006 (1.00) l C. )

REFERENCE, i

Operations Procedure (Normal Conditions) Step D. )

1 ANSWER: 007 (1.00)

B. ,

REFERENCE:

Operations Procedure. Abnormal and Emergency Conditions. A.9, ANSWER: 008 (1.00)

D.

REFERENCE:

Operations Procedure. Abnormal and Emergency Conditions C.4.a.

ANSWER: 009 (1.00)

C.

REFERENCE:

Operations-Procedure. Abnormal and Emergency Conditions. A.13.d.

ANSWER: 010- (1.00)

B.

REFERENCE:

ISU Emergency Plan, page 4, step 16.

._ - - . . - J

ANSWER: 011 (1.00)

B.

REFERENCE:

ISU Technical Specifications. Section 2.1.3.

ANSWER: 012 (1.00)

B.

REFERENCE:

10 CFR 20.

l ANSWER: 013 (1.00) l B.

REFERENCE:

ISU Technical Specifications. Section 6.1.3.

ANSWER: 014 (1.00)

D.

REFERENCE:

ISU Technical Specifications, Section 4.3.3.

ANSWER: 015 (1.00)

D.

REFERENCE:

ISU Technical Specifications Section 6.1.3.

ANSWER: 016 (2.00)

A.2: B.2: C,3: D1

REFERENCE:

ISU Technical Specifications. Section 1.0.  !

l 1

l l

l l

1 I

C. FACILITY AND RADIATION MONITORING SYSTEMS l ANSWER: 001 (1.00)

! C.

REFERENCE:

Facility Information, pg. 60.

l l ANSWER: 002 (1.00) .

C. l

REFERENCE:

Facility Information, pg. 48.

ANSWER: 003 (1.00) l l

B.

REFERENCE:

Facility Information, pg. 34.

l ANSWER: 004 (1.00) i A.  !

REFERENCE:

Facility Information, pg. 25.

ANSWER: 005 (1.00) ,

l B.

REFERENCE:

Facility Information, pg. 49. 1 i

ANSWER: 006 (1.00)  !

D.

REFERENCE:

i Technical Specifications Table 3-2.

ANSWER: 007 (1.00)

D.

REFERENCE:

UTR-10 Standby Power Supply.

ANSWER: 008 (1.00)

A.

REFERENCE:

UTR-10 Reactor Training Manual, " Neutron Travel and Neutron Sources " pgs. 1-68 through I- 72.

ANSWER: 009 (1.00)

D.

REFERENCE:

Reactor Operations (Normal Conditions). E.1.1 ANSWER: 010 (1.00)

B.

REFERENCE:

Facility Information, pg. 61.

l .

ANSWER: 011 (1.00)

D.

l

REFERENCE:

Facility Information. Nuclear Instrument / Safety System Diagram.

ANSWER: 012 (1.00) l A.

l

REFERENCE:

Facility Information, pg. 48.

i I

ANSWER: 013 (1.00)  !

C.

REFERENCE:

Facility Information, pg. 48.

ANSWER: 014 (1.00)

C.

REFERENCE:

Facility Information. Nuclear Instrument / Safety System Diagram.

ANSWER: 015 (1.00)

B.

REFERENCE:

Facility Information, pg. 32.

ANSWER: 016 (1.00)

A.

REFERENCE:

Facility Information, pg. 44.

ANSWER: 017 (1.00)

8. ,

REFERENCE:

Facility Information, pg. 42.

ANSWER: 018 (1.00) l C. 1 REFERENCE- )

Facility Information, pg. 27.

l 1

l l

A. REACTOR THEORY THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS l

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

t 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 019 a b c d l

l l

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

l B. NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS 1

ANSWER SHEET MULTIPLE CH0 ICE (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 l

014 a b c d l

015 a b c d 016 a b c d

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

i 1

1 C. FACILITY AND RADIATION MONITORING SYSTEMS ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)

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

l 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 1

007 a b c d 008 a b c d 009 b c d a

l 010 b c d a

l 011 a b c d l 012 a b c d 013 a b c d 014 a b c d 015 a b c d i'

016 a b c d 017 a b c d 018 a b c d i

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

1 i

EQUATIDN SHEET 0-mt oAT CR (1-Keff)3 - CR2 (1-Keff)2 3

SUR - 26.06/7 P = Po 10 5UR(O P-Po e"") 7 - (t*/p) + [(B-0)/A,,,p]

A,,,- 0.1 seconds'2 DR31D 2 - DR22 0*

2 DR - DRo e " DR - 6CiE/D p - (Keff-1)/Keff 1 eV - 1.6x10- ' watt-sec.

1 Curie - 3.7x1020dps 1 gallon water - 8.34 pounds I 1 Btu - 778 ft-lbf F - 9/5 C + 32 1 Mw - 3.41x106BTU /hr C - 5/9 ( F - 32) i

REGULATING ROD WORTH CURVF_ FOR LEU-01 F Ut- L LUAU .

0.25 - REG DRIVEN FROM 100% AT 80 DEGREES (SHIM AT 33.7%) -0.25 1______ 2 T t t_ i ,

0.20 -

j , - __ - -0.20

_f t I i _

_j_ _

j _._ __

j n

\ .

_ y

, ( _ _

i 4

-0.15 0.15 - l l , ,

/

• i . ,

M

! e i , i f i[

/ $ I ._

I 3 8

/'.

+ '

e> -

d

. . / _

a i i / i a >

O  ? I

/ l 4 w

-0.10 g 8 0.10 - , _ _ ,  ; / ,l m , , .

,/

m u

e i '

/

j s

0.05 / 4 i , ,

O.05

/ '

. /

/ __

/

O.00 , , ,, ,

,, , , , , , , , , , -0.00 0 10 20 30 40 50 60 70 80 90 100 reg position, s

(

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - - - _ _ - - _ _ _ - - _ _ _ _. .-_