ML091070556

Initial Examination Report No. 50-188/OL-09-01, Kansas State University Triga Reactor

ML091070556
Person / Time
Site:	Kansas State University
Issue date:	04/28/2009
From:	Johnny Eads Research and Test Reactors Branch B
To:	Whaley M Kansas State University, Univ of Kansas
Doyle, P V, NRR/DPR,301-415-1058
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ML090260033	List: ML091070556 ML091070600
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50-188/OL-09-01 50-188/OL-09-01
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Text

April 28, 2009 Mr. Michael Whaley, Manager KSU Nuclear Reactor Facility Department of Mechanical and Nuclear Engineering 112 Ward Hall Kansas State University Manhattan, KS 66506-2500

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-188/OL-09-01, KANSAS STATE UNIVERSITY TRIGA REACTOR

Dear Mr. Whaley:

During the week of March 30, 2009, the Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Kansas State University TRIGA reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Paul V. Doyle Jr. at (301) 415-1058 or via internet e-mail Paul.Doyle@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-188

Enclosures:

1. Initial Examination Report No.

50-188/OL-09-01

2. Written examination with facility comments incorporated cc w/o encl:

ML091070556 NRR-074 OFFICE PRTB:CE IOLB:LA PRTB:SC NAME PDoyle:mxc CRevelle JEads DATE 04/17/2009 04/202009 04/28/2009

Kansas State University Docket No. 50-188 cc:

Office of the Governor State of Kansas Topeka, KS 66612 Thomas A. Conley, RRPJ, CHP, Section Chief Radiation and Asbestos Control KS Dept of Health & Environment 1000 SW Jackson, Suite 320 Topeka, KS 66612-1366 Mayor of Manhattan P.O. Box 748 Manhattan, KS 66502 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-188/OL-09-01 FACILITY DOCKET NO.:

50-188 FACILITY LICENSE NO.:

R-88 FACILITY:

Kansas State University TRIGA Reactor EXAMINATION DATES:

March 31, 2009 - April 02, 2009 SUBMITTED BY:

______/RA/____________________

04/17/09_

Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

On March 31, and April 01, 2009, the NRC administered written examinations and operating tests to three reactor operator initial candidates, one reactor operator retake candidate, and one senior reactor operator initial candidate. All five candidates passed all portions of their respective examinations.

REPORT DETAILS

1.

Examiners:

Paul V. Doyle Jr., Chief Examiner, NRC

2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 4/0 N/A 4/0 Operating Tests 4/0 1/0 5/0 Overall 4/0 1/0 5/0

3.

Exit Meeting:

Paul Doyle, Chief Examiner, NRC P. Michael Whaley, Reactor Manager, KSU The exit meeting was held on April 02, 2009. The examiner thanked the reactor manager for his support in the administration of the examinations. The reactor manager had comments on written examination questions B.01, (No correct answer) B.08 (change answer key for part d, from 3 to 1), C.07 (question should be rewritten for clarity) and C.11 (No correct answer). The examination and answer key attached to this report have been corrected.

ENCLOSURE 1

OPERATOR LICENSING INITIAL EXAMINATION With Answer Key KANSAS STATE UNIVERSITY Week of March 30, 2009

Section A Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 1 QUESTION A.01

[1.0 point]

During the minutes following a reactor scram, reactor power decreases on a negative 80 second period, corresponding to the half-life of the longest lived delayed neutron precursor, which is approximately:

a. 20 seconds.

b. 40 seconds.

c. 55 seconds.

d. 80 seconds.

QUESTION A.02

[1.0 point]

Which ONE statement below describes a positive fuel temperature coefficient?

a. When fuel temperature increases, positive reactivity is added.

b. When fuel temperature decreases, positive reactivity is added.

c. When fuel temperature increases, negative reactivity is added.

d. When fuel temperature increases, reactor power decreases.

QUESTION A.03

[1.0 point]

A reactor is critical at 18.1 inches on a controlling rod. The controlling rod is withdrawn to 18.4 inches. The reactivity inserted is 14.4 cents. What is the differential rod worth?

a. 14.4 cents/inch at 18.25 inches.

b. 14.4 cents/inch only between 18.1 and 18.4 inches.

c. 48 cents/inch at 18.4 inches.

d. 48 cents/inch at 18.25 inches.

QUESTION A.04

[1.0 point]

Which ONE of the following describes the response of the subcritical reactor to equal insertions of positive reactivity as the reactor approaches critical? Each reactivity insertion causes:

a. a SMALLER increase in the neutron flux, resulting in a LONGER time to reach equilibrium.

b. a SMALLER increase in the neutron flux, resulting in a SHORTER time to reach equilibrium.

c. a LARGER increase in the neutron flux, resulting in a LONGER time to reach equilibrium.

d. a LARGER increase in the neutron flux, resulting in a SHORTER time to reach equilibrium.

Section A Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 2 QUESTION A.05

[1.0 point]

A 1/M curve is being generated as fuel is loaded into the core. After some fuel elements have been loaded, the count rate existing at that time is taken to be the new initial count rate, Co. Additional elements are then loaded and the inverse count rate ratio continues to decrease. As a result of changing the initial count rate:

a. criticality will occur with the same number of elements loaded as if there were no change in the initial count rate.

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

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

d. criticality will be completely unpredictable.

QUESTION A.06

[1.0 point]

Delayed neutrons are considered to be more effective than prompt neutrons because delayed neutrons have a:

a. higher reproduction factor.

b. higher resonance escape probability.

c. lower thermal utilization factor.

d. higher thermal utilization factor.

QUESTION A.07

[1.0 point]

The major contribution to the production of Xenon-135 in a reactor operating at full power is:

a. directly from the fission of U-235.

b. from the radioactive decay of iodine.

c. from the radioactive decay of promethium.

d. directly from the fission of U-238.

QUESTION A.08

[1.0 point]

A reactor is being started up, and has a count rate of 45 cps when Keff = 0.980. When the count rate reaches 90 cps, the new Keff will be:

a. 0.986.

b. 0.988

c. 0.990.

d. 0.992

Section A Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 3 QUESTION A.09

[1.0 point]

A reactor is operating at a constant power level with equilibrium xenon. Reactor power is then doubled. The equilibrium xenon level at the higher power level will be:

a. higher than its value at the lower power level, but not twice as high.

b. twice as high.

c. more than twice as high.

d. the same as at the lower power level.

QUESTION A.10

[1.0 point]

Which ONE of the following is the principal source of energy (heat generation) in the reactor 15 minutes following a reactor shutdown from extended operation at 100% power?

a. Production of delayed neutrons.

b. Subcritical multiplication.

c. Spontaneous fission of U-238.

d. Decay of fission products.

QUESTION A.11

[1.0 point]

Which ONE of the following does NOT affect the Effective Multiplication Factor Keff?

a. The moderator-to-fuel ratio.

b. The moderator temperature.

c. The physical dimensions of the core.

d. The strength of an installed neutron source.

QUESTION A.12

[1.0 point]

The reactor is to be pulsed. The projected pulse will add TWICE as much reactivity as the last pulse performed. In relation to the last pulse, for the projected pulse peak power will be:

a. about four times larger and the energy released will be about four times larger.

b. about two times larger and the energy released will be about four times larger.

c. about four times larger and the energy released will be about two times larger.

d. about two times larger and the energy released will be about two times larger.

Section A Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 4 QUESTION A.13

[1.0 point]

What is the kinetic energy range of a thermal neutron?

a. > 1 MeV

b. 100 KeV - 1 MeV

c. 1 eV - 100 KeV

d. < 1 eV QUESTION A.14

[1.0 point]

Given the following data, which ONE of the following is the closest to the half life of the material?

TIME ACTIVITY 0

2400 cps 10 min.

1757 cps 20 min.

1286 cps 30 min.

941 cps 60 min.

369 cps

a. 11 minutes

b. 22 minutes

c. 44 minutes

d. 51 minutes QUESTION A.15

[1.0 point]

During a fuel loading of the core, as the reactor approaches criticality, the value of 1/M:

a. Increases toward one

b. Decreases toward one

c. Increases toward infinity

d. Decreases toward zero QUESTION A.16

[1.0 point]

Which one of the following statements correctly describes the property of a GOOD MODERATOR?

a. It slows down fast neutrons to thermal energy levels via a large number of collisions.

b. It reduces gamma radiation to thermal energy levels via a small number of collisions.

c. It slows down fast neutrons to thermal energy levels via a small number of collisions.

d. It reduces gamma radiation to thermal energy levels via a large number of collisions.

Section A Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 5 QUESTION A.17

[2.0 points, 0.4 each]

A fissile material is one which will fission upon the absorption of a THERMAL neutron. A fertile material is one which will produce a fissile material after absorption of a neutron and subsequent decay. Identify each of the isotopes listed as either fissile or fertile.

a.

90Th232

b.

92U233

c.

92U235

d.

92U238

e.

94Pu239 QUESTION A.18

[1.0 point]

The table provided lists data taken during a core loading. Estimate the number of fuel elements needed to go critical.

a. 18

b. 22

c. 26

d. 30 QUESTION A.19

[1.0 point]

Which ONE of the following is the definition of the term Cross-Section?

a. The probability that a neutron will be captured by a nucleus.

b. The most likely energy at which a charge particle will be captured.

c. The length a charged particle travels past the nucleus before being captured.

d. The area of the nucleus including the electron cloud.

Count Rate Number of Fuel Elements 842 2

936 4

1123 7

1684 12 2806 16

Section B Normal, Abnormal, Emergency and Radiological Controls Procedures Page 6 QUESTION B.01

[1.0 point]

Question deleted per facility comment (no correct answer).

In accordance with the Technical Specifications, which ONE condition below is NOT permissible when the reactor is operating?

a. Maximum available reactivity above cold, clean condition = $3.00.

b. Primary water temperature = 110EF.

c. Pool water conductivity = 2 micromho/cm.

d. Fuel temperature = 400EC.

QUESTION B.02

[1.0 point]

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.

QUESTION B.03

[1.0 point]

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 B.04

[1.0 point]

In accordance with Technical Specifications, which ONE of the following interlocks may be bypassed during fuel loading operations?

a. Movement of any rod except the transient rod.

b. Shim and regulating rod withdrawal with less than two counts per second on the start-up channel.

c. Simultaneous manual withdrawal of two rods.

d. Application of air to the transient rods unless regulating and shim rods are fully inserted.

Section B Normal, Abnormal, Emergency and Radiological Controls Procedures Page 7 QUESTION B.05

[1.0 point]

Which ONE of the following gases is now used instead of air as the prime mover in the pneumatic tube system?

a. Argon.

b. Helium.

c. Nitrogen.

d. Oxygen.

QUESTION B.06

[1.0 point]

The 5 R/hr evacuation alarm has sounded. In addition, the gamma radiation level in the hallway outside the reactor control room is 150 mR/hr. Which ONE of the following actions should be taken?

a. The Site Boundary area shall be evacuated.

b. All personnel in the Operations Boundary area shall assemble at Ward Hall Emergency Assembly Area 1 or 2.

c. The University Radiation Safety Officer should be immediately summoned to confirm the radiation levels.

d. All personnel in the Site Boundary area shall assemble in the Operations Boundary area.

QUESTION B.07

[1.0 point]

In accordance with Experiment No. 30, "Pulsed Operation, Amended, the reactor is pulsed starting from a subcritical configuration when:

a. it is desired to pulse over a wider range of power.

b. the reactor cannot be made critical.

c. the available excess reactivity is less than the worth of the pulse rod.

d. the time required to reach criticality might adversely affect the purpose of the pulse experiment.

QUESTION B.08

[2.0 points, 1/2 each]

Select the MODE from Column B when the Scrams/Interlocks from Column A are required to be effective. Modes in Column B may be used once, more than once, or not at all.

Column I (Scrams/Interlocks)

Column II (Mode)

a. Safety Channel at 110% of full power

1. Steady State only

b. Fuel Temperature at 450EC.

2. Pulse Only

c. Ion Chamber Power Supply Failure

3. Both Pulse and Steady State

d. Simultaneous manual withdrawal of two rods.

4. Fuel loading only

Section B Normal, Abnormal, Emergency and Radiological Controls Procedures Page 8 QUESTION B.09

[1.0 point]

The OPERATIONS BOUNDARY is defined as:

a. Room 110 of Ward Hall.

b. Ward Hall and adjacent fenced areas.

c. Facility Control Center.

d. Nuclear Engineering Departmental Office.

QUESTION B.10

[1.0 point]

In accordance with 10 CFR 20, the "Annual Limit on Intake (ALI)" 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. 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 equivalent of 5 rems.

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

QUESTION B.11

[1.0 point]

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 B.12

[1.0 point]

"Protective Action Guides are:

a. specific instrument readings, observations, dose rates, etc., which provide thresholds for establishing emergency classes.

b. projected dose equivalents to individuals in the general population which warrants protective actions following a nuclear incident.

c. dose equivalents that are projected to be received by individuals in a population group from a contaminating event if no protective actions were taken.

d. instructions that detail the implementation actions and methods required to achieve the objectives of the emergency plan.

Section B Normal, Abnormal, Emergency and Radiological Controls Procedures Page 9 QUESTION B.13

[2.0 points, 1/2 each]

Match the annual dose limit values to the type of exposure.

Type of Exposure Annual Dose Limit Value

a. Extremities

1. 0.1 rem.

b. Lens of the Eye

2. 5.0 rem.

c. Occupational Total Effective Dose Equivalent (TEDE)

3. 15.0 rem.

d. TEDE to a member of the public

4. 50.0 rem.

QUESTION B.14

[1.0 point]

An accessible area within the facility has a general radiation level of 325 mrem/hour. What would be the EXPECTED posting for this area?

a. "Caution, Airborne Radioactivity Area"

b. "Caution, Radiation Area"

c. "Danger, High Radiation Area"

d. "Grave Danger, Very High Radiation Area" QUESTION B.15

[1.0 point]

A radioactive source generates a reading of 100 mr/hr at a distance of 10 feet. With two inches of lead shielding the reading drops to 50 mr/hr at a distance of 10 feet. If you were to add another four inches of the same type of shielding, the reading at 10 feet would drop to

a. 25 mr/hr

b. 121/2 mr/hr

c. 61/4 mr/hr

d. 3 mr/hr QUESTION B.16

[1.0 point]

Which ONE of the following is the 10 CFR 20 definition of TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)?

a. The sum of the deep does equivalent and the committed effective dose equivalent.

b. The dose that your whole body receives from sources outside the body.

c. The sum of the external deep dose and the organ dose.

d. The dose to a specific organ or tissue resulting from an intake of radioactive material.

Section B Normal, Abnormal, Emergency and Radiological Controls Procedures Page 10 QUESTION B.17

[1.0 point]

You place a radiation monitor neat to the demineralizer during reactor operation. If you were to open the window on the detector you would expect the meter reading to (Assume no piping leaks)

a. increase, because you would now be receiving signal due to H3 and O16 betas.

b. remain the same, because the Quality Factors for gamma and beta radiation are the same.

c. increase, because the Quality Factor for betas is greater than for gammas.

d. remain the same, because you still would not be detecting beta radiation.

QUESTION B.18

[1.0 point]

Automatic scram signals are initiated by 1) loss of high voltage to nuclear instrumentation, 2) high linear channel power, 3) high safety channel power, 4) high fuel temperature, and 5) short reactor period. Of these, the scram signals required by the Technical Specifications are:

a. short period, high linear channel power, high safety channel power, high fuel temperature.

b. high linear channel, high safety channel power, high fuel temperature, loss of high voltage.

c. high linear channel power, loss of high voltage, short period, high fuel temperature.

d. high safety channel power, short period, high fuel temperature, loss of high voltage.

Section C Facility and Radiation Monitoring Systems Page 11 QUESTION C.01

[1.0 point]

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.

QUESTION C.02

[1.0 point]

During a loss of building electrical power:

a. power to reactor instrumentation will not be lost due to a fast transfer (less than 50 msec) to the reserve supply.

b. power to reactor instrumentation will be restored following a 5 second time delay as transfer to the reserve supply occurs.

c. power will be lost to reactor instrumentation but will be automatically restored when building power returns.

d. power will be lost to reactor instrumentation and will not return until building power returns and the line conditioner is manually reset.

QUESTION C.03

[1.0 point]

The reactor is in the steady state mode with the transient rod shock absorber fully inserted (full down) and no air applied. The shock absorber is moved upward, and the operator then attempts to apply air to the transient rod.

Which ONE of the following results?

a. The air solenoid blocks air to the transient rod.

b. The transient rod moves up until it reaches the shock absorber.

c. The shock absorber returns to its full down position.

d. The shim rod moves into the core.

QUESTION C.04

[1.0 point]

Coolant flow in the demineralizer loop of the reactor coolant system is measured by:

a. differential pressure across the filter.

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

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

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

Section C Facility and Radiation Monitoring Systems Page 12 QUESTION C.05

[1.0 point]

Thermocouples in an instrumented TRIGA fuel element measure temperature at the:

a. interior surface of the cladding.

b. interior of the fuel.

c. outer surface of the fuel.

d. center of the zirconium rod.

QUESTION C.06

[1.0 point]

Which ONE of the following describes the purpose of the Pull Rod in the control rod drive assembly?

a. Provides rod full out position indication.

b. Provides a means for manually adjusting the rod position by pulling rod out.

c. Actuates the rod down microswitch.

d. Automatically engages the control rod on a withdraw signal.

QUESTION C.07

[1.0 point]

Which ONE of the following is the purpose of the mechanical filter installed in the cleanup loop?

a. Maintain low electrical conductivity of the water and a neutral pH.

b. Maintain optical transparency and minimal radioactivity of the water.

c. Maintain a neutral pH and optical transparency of the water.

d. Maintain minimal radioactivity and low electrical conductivity of the water.

QUESTION C.08

[1.0 point]

Which ONE of the following describes the action of the rod control system to drive the magnet draw tube down after a dropped rod? Downward motion of the draw tube is initiated by

a. deenergizing the rod magnet.

b. closing the contact on the MAGNET DOWN limit switch.

c. closing the contact on the ROD DOWN limit switch.

d. de-energizing both contact light (DS317) and the MAGNET UP limit switch.

Section C Facility and Radiation Monitoring Systems Page 13 QUESTION C.09

[1.0 point]

When the percent power channel is used for neutron detection, how is the gamma flux accounted for?

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

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

c. The gamma flux is canceled 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 C.10

[1.0 point]

The flow rate in the primary loop is maintained by which ONE of the following methods?

a. A flow orifice in the primary piping.

b. Adjustment of the filter pressure drop.

c. Adjustment of primary pump speed.

d. Throttling the discharge valve of the primary pump.

QUESTION C.11

[1.0 point] Question deleted per facility comment (no correct answer).

The following conditions exist in the primary and secondary cooling systems:

Outside air temperature = 0°F Temperature of secondary flow from cooling tower = 60°F Primary temperature = 105°F Set control temperature

= 100°F Under these conditions:

a. the cooling tower fan is operating at low speed.

b. the cooling tower fan is operating at high speed.

c. the cooling tower fan is not operating.

d. the cooling tower fan operates at low speed until the primary temperature drops below the set control temperature.

QUESTION C.12

[2.0 points, 1/2 each]

Select from column B the actual rod movement that would result from attempting to move the rods in column A.

(Items in column B may be used once, more than once or not at all.

Column A (Attempted Rod Move)

Column B (Result)

a. Attempt to withdraw reg rod (pulse mode).

1. Shim rod moves up.

b. Attempt to withdraw both shim and reg rods (steady state mode)

2. Reg rod moves up.

c. Attempt to withdraw both pulse and reg rod (steady state mode).

3. Shim & reg rods move up.

d. Shim and pulse rods are up and attempt to withdraw pulse rod

4. Pulse rod moves up.

(steady state mode).

5. No rod motion.

Section C Facility and Radiation Monitoring Systems Page 14 QUESTION C.13

[1.0 point]

The continuous air monitors are calibrated to detect the presence of:

a. noble gases from a leaking fuel element.

b. Ar41

c. N16

d. I131 QUESTION C.14

[1.0 point]

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.

QUESTION C.15

[1.0 point]

The central thimble is an aluminum tube extending from the top of the reactor tank and terminating:

a. below the bottom grid plate.

b. at the bottom grid plate.

c. at the midpoint of the core.

d. at the top grid plate.

QUESTION C.16

[1.0 point]

The reactor is operating in the pulse mode when a reactor scram occurs. The transient rod solenoid valve:

a. is energized by the scram circuitry, which opens the valve and removes air from the cylinder.

b. is de-energized by the scram circuitry, which closes the valve and removes air from the cylinder.

c. is energized by a timer, which closes the valve and removes air from the cylinder.

d. is de-energized by a timer, which opens the valve and removes air from the cylinder.

Section C Facility and Radiation Monitoring Systems Page 15 QUESTION C.17

[1.0 point]

In the control rod drive system, the contact light will be extinguished if the MAGNET DOWN microswitch is

a. actuated AND the ROD DOWN microswitch is actuated.

b. NOT actuated AND the ROD DOWN microswitch is actuated.

c. actuated OR the ROD DOWN microswitch is NOT actuated.

d. NOT actuated OR the ROD DOWN microswitch is actuated.

QUESTION C.18

[1.0 point]

The water monitor vessel contains:

a. a temperature probe, a pressure probe, and a GM tube.

b. a temperature probe, a conductivity probe, and a pressure probe.

c. a conductivity probe, a pressure probe, and a GM tube.

d. a conductivity probe, a temperature probe, and a GM tube.

QUESTION C.19

[1.0 point]

Which ONE of the following is the flow through the primary loop and the cleanup loop?

a. 120 gpm total flow with 10 gpm through the cleanup loop

b. 110 gpm total flow with 10 gpm through the cleanup loop

c. 120 gpm total flow with 20 gpm through the cleanup loop

d. 110 gpm total flow with 20 gpm through the cleanup loop

Section A Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 16 A.01 c

REF:

DOE Reference, Module 4, Table 1 on page 12. NRC Exam March 2000.

A.02 a

REF:

DOE Reference, Module 3, Reactivity Coefficients and Reactivity Defects, page 37. NRC Exam March 2000.

A.03 d

REF:

DOE Reference, Module 3, Integral and Differential Rod Worth, page 51. NRC Exam March 2000.

A.04 c

REF:

Standard NRC question. NRC Exam March 2000.

A.05 a

REF:

DOE Reference, Module 4, page 6. NRC Exam July 2000.

A.06 b

REF:

DOE Reference, Module 4, Last ¶ on page 12. NRC Exam July 2000.

A.07 b

REF:

DOE Reference, Module 3, Production & Removal of Xe135, page 35. NRC Exam July 2000.

A.08 c

REF:

DOE Reference, Module 4, bottom of page 4. NRC Exam July 2000.

A.09 a

REF:

DOE Reference, Module 3, Xenon, page 37. NRC Exam June, 2003.

A.10

d.

REF:

DOE Reference, Module 4, page 33. Exam 5 A.11 d

REF:

NRC Exam January, 2005. DOE Reference, Module 3, pages 2-9.

A.12

c.

REF:

NRC Exam January, 2005.

A.13

d.

REF:

Reference 1, Module 2, Neutron Moderation, p. 23, Exam 7 A.14 b

REF:

Standard NRC Question A = A0 e-T (22 minutes). NRC Exam October, 2006.

A.15 d

REF:

NRC Exam October, 2006. DOE Reference, Module 4, Theory ( Operations), E.O. 1.4, pg. 7 A.16 c

REF:

NRC Exam October, 2006. DOE Reference, Module 2, Enabling Objective 2.13.

A.17 a, FER, b, FISS; c, FISS; d, FER; e, FISS REF:

DOE Reference, Module 1, pages 51 and 52.

A.18 b

REF:

(See attached sketch, ~ 22 fuel elements)

A.19 a

REF:

Reactor Training Manual - Cross Section.

Section B Normal, Abnormal, Emergency and Radiological Controls Procedures Page 17 B.01 a

Question Deleted, No correct answer due to changes to the Technical Specifications.

REF:

NRC Exam March 2000.

B.02 a

REF:

NRC Exam March 2000. KSU Operation, Test, and Maintenance Procedures, Procedure No. 21.

B.03 c

REF:

NRC Exam March 2000.

B.04 b

REF:

NRC Exam March 2000. Technical Specifications, Table II B.05 b

REF:

New question from latest SAR.

B.06 b

REF:

NRC Exam March 2000. Emergency Plan, 3.5.

B.07 b or c REF:

NRC Exam March 2000. Experiment No. 30.

B.08 a,1; b,2; c,3; d,3. 1 Answer changed per facility comment.

REF:

NRC Exam March 2000. Technical Specifications, Table II.

B.09 a

REF:

NRC Exam April, 2002. Emergency Plan, section 1.1.

B.10 a

REF:

NRC Exam April, 2002. Radiation Protection Program, page A-2.

B.11 b

REF:

NRC Exam April, 2002. Emergency Plan, section 6.2.

B.12 b

REF:

NRC Exam April, 2002. Emergency Plan, section 7.1.

B.13 a, 4; b, 3; c, 2; d, 1 REF:

10 CFR 20 §§ 1201.a(2)(ii), 1201.a(1), 1201.a(2)(i), 1301 B.14 c

REF:

10CFR20.???????

B.15 b

REF:

2 = one-half thichness (T1/2). Using 3 half-thickness will drop the dose by a factor of (1/2)3 =. 100/8 = 12.5 B.16 a

REF:

10 CFR 20.1003 Definitions B.17 d

REF:

BASIC Radiological Concept (Betas don't make it through piping.)

B.18 b

REF:

NRC Exam March 2000. Technical Specifications, Table I.

Section C Facility and Radiation Monitoring Systems Page 18 C.01 d

REF:

NRC Exam March 2000. KSU Training Manual, General Characteristics, § 9, Transient Rod Drive Mechs.

C.02 d

REF:

NRC Exam March 2000. KSU Training Manual, General Characteristics, § 7, Reactor Instrumentation.

C.03 a

REF:

NRC Exam March 2000. KSU Operation, Test and Maintenance Procedures, Procedure No. 5, Part 1.

C.04 b

REF:

NRC Exam March 2000. KSU Training Manual, General Characteristics, Section 6, Coolant System, Fig. 5.

C.05 b

REF:

NRC Exam March 2000. KSU Training Manual, General Characteristics, Section 7.1, Measurement.

C.06 c

REF:

NRC Exam March 2000. KSU Training Manual, General Characteristics, Section 8.2, Circuit Operations.

C.07 b

REF:

NRC Exam March 2000. KSU Training Manual, General Characteristics, Section 6, Coolant System.

C.08 c

REF:

NRC Exam March 2000. KSU Training Manual, General Characteristics, Section 8.2, Circuit Operations.

C.09 b

REF: NRC Exam April, 2002. Training Manual, page A1-15.

C.10 a

REF: NRC Exam June, 2003. Training Manual, page A1-10.

C.11

c.

Question Deleted. No correct answer due to changes to the secondary cooling system as part of the license power increase.

REF:

NRC Exam January, 2005. Training Manual, page A1-14.

C.12 a, 5; b, 5; c, 4; d, 4.

REF:

NRC Exam March 2000. KSU Operation, Test and Maintenance Procedures, Procedure No. 5, Part 1.

C.13 d

REF:

NRC Exam March 2000. KSU Operation, Test and Maintenance Procedures, Procedure No. 8.

C.14 b

REF: NRC Exam April, 2002. Training Manual, page A1-6.

C.15 a

REF: NRC Exam April, 2002. Training Manual, page A1-7.

C.16 d

REF: NRC Exam April, 2002. Training Manual, page A1-18.

C.17 b

REF: NRC Exam April, 2002. Training Manual, page A1-17.

C.18 d

REF: NRC Exam April, 2002. Training Manual, page A1-10.

C.19 b

REF:

NRC Exam January, 2005. SAR, page 5-3.