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Examination Report No. 50-284/OL-18-02, Idaho State University
	ML18291A965
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Site:	Idaho State University
Issue date:	10/15/2018
From:	Anthony Mendiola; Research and Test Reactors Oversight Projects Branch
To:	Dunzik-Gougar M; Idaho State University
	Randiki C
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October 15, 2018 Dr. Mary Lou Dunzik-Gougar, Reactor Administrator College of Science and Engineering Idaho State University 921 S. 8th Avenue, MS 8060 Pocatello, ID 83209-8060

SUBJECT:

EXAMINATION REPORT NO. 50-284/OL-18-02, IDAHO STATE UNIVERSITY

Dear Dr. Dunzik-Gougar:

During the week of September 17, 2018, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Idaho State University reactor. The examinations were 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 Ms. Michele DeSouza at (301) 415-0747 or via internet e-mail Michele.DeSouza@nrc.gov.

Sincerely,

/RA/

Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 50-284

Enclosures:

1. Examination Report No. 50-284/OL-18-02

2. Written examination cc: w/o enclosures: See next page

ML18291A965 NRR-079 OFFICE NRR/DLP/PROB/CE NRR/DLP/IOLB/OLA NRR/DLP/PROB/BC NAME MDeSouza CJRandiki AMendiola DATE 09/20/2018 10/15/2018 10/15/2018 Idaho State University Docket No. 50-284 cc:

Dr. Cornelis J. Van der Schyf Idaho State University Vice President for Research and Dean of the Graduate School Mail Stop #8130 Pocatello, ID 83209 Dr. Richard Brey, Radiation Safety Officer Technical Safety Office Idaho State University P.O. Box 8106 Pocatello, ID 83209-8106 Director Idaho Dept. of Environmental Quality 1410 North Hilton Boise, ID 83606 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida, Gainesville, FL 32611 Maxwell Daniels, Reactor Supervisor Idaho State University Campus Box 8060 Pocatello, ID 83209-8060

U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-284/OL-18-02 FACILITY DOCKET NO.: 50-284 FACILITY LICENSE NO.: R-110 FACILITY: AGN-201 EXAMINATION DATES: September 17-20, 2018 SUBMITTED BY: /RA/ 09/20/2018 Michele DeSouza, Chief Examiner Date

SUMMARY

During the week of September 17, 2018, the NRC administered an operator licensing examination to four Reactor Operator (RO) candidates and two RO retake candidates. The four RO candidates and two RO retake candidates passed all applicable portions of the examination(s).

REPORT DETAILS

1. Examiner: Michele DeSouza, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 6/0 0/0 6/0 Operating Tests 4/0 0/0 4/0 Overall 6/0 0/0 6/0

3. Exit Meeting:

Michele C. DeSouza, Chief Examiner, NRC Maxwell Daniels, Reactor Supervisor, Idaho State University Mary Lou Dunzik-Gougar, Reactor Administrator, Idaho State University Per discussion with the facility, prior to administration of the examination, adjustments were accepted. Upon completion of the examination, the NRC Examiner met with facility staff representatives to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.

ENCLOSURE 1

U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Idaho State University REACTOR TYPE: AGN-201 DATE ADMINISTERED: 09/19/2018 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature ENCLOSURE 2

Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A01 a b c d ___

A02 a b c d ___

A03 a ___ b ___ c ___ d ___ (0.25 each)

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a b c d ___

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a b c d ___

A18 a b c d ___

A19 a b c d ___

A20 a b c d ___

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

Category B - Normal/Emergency Operating Procedures and Radiological Controls ANSWER SHEET Multiple Choice (Circle or X your choice)

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

B01 a b c d ___

B02 a b c d ___

B03 a b c d ___

B04 a b c d ___

B05 a b c d ___

B06 a b c d ___

B07 a b c d ___

B08 a b c d ___

B09 a b c d ___

B10 a b c d ___

B11 a b c d ___

B12 a b c d ___

B13 a b c d ___

B14 a b c d ___

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a ___ b ___ c ___ d ___ (0.50 each)

B19 a b c d ___

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

Category 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.

C01 a ___ b ___ c ___ d ___ (0.50 each)

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a ___ b ___ c ___ d ___ e ___ f ___ g ___ h ___ (0.25 each)

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

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

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

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

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor 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 and each Answer sheet.

6. Mark your Answers on the Answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

7. The point value for each question is indicated in [brackets] after the question.

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

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

10. Ensure all information you wish to have evaluated as part of your Answer is on your Answer sheet. Scrap paper will be disposed of immediately following the examination.

11. To pass the examination you must achieve a grade of 70 percent or greater in each category.

12. There is a time limit of three (3) hours for completion of the examination.

EQUATION SHEET

( )2 eff = 0.1sec 1 Q&= m&cP T = m&H =UAT Pmax =

(2 )

t P = P0 e S S SCR = * =1x104 sec 1 K eff eff + &

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR(t )

P= P0 1 K eff CR1 1 K eff1 1 K eff

M= SDM = =

1 K eff 2 K eff

0.693 K eff 2 K eff1

+ T1 =

eff + & 2 K eff1 K eff 2 K eff 1

= DR = DR0 e t 2 DR1 d1 = DR2 d 2 2

K eff 6 Ci E (n) ( 2 )2 = (1 )2 DR =

R2 Peak2 Peak1 DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lb °F = 9/5 °C + 32 1 gal (H2O) 8 lb °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lb/°F cp = 1 cal/sec/gm/°C

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01 [1.0 point]

Which ONE of the following is a reason that, regardless of the initial power level the stable negative period following a scram is always the same value (-80 seconds)?

a. The nuclear instrument reads the constant count rate from a neutron source.

b. The rate of power change is dependent on a mean lifetime of the shortest lived delayed neutron precursor.

c. The delayed neutrons are born at the same rate as prompt neutrons after shutdown resulting in a constant neutron count rate.

d. The rate of power change is dependent on a mean lifetime of the longest lived delayed neutron precursors.

QUESTION A.02 [1.0 point]

Which ONE of the following isotopes has the HIGHEST thermal neutron cross section?

a. Cd-112

b. Sm-149

c. Xe-135

d. U-235 QUESTION A.03 [1.0 point, 0.25 each]

Match the following neutron interactions in Column A with its correct definition in Column B.

(Each used only once)

Column A Column B

a. Fission 1. Neutron enters nucleus, forms a compound nucleus, then decays by gamma emission

b. Scattering 2. Particle enters nucleus, forms a compound nucleus and is excited enough to eject a new particle with incident neutron remaining in nucleus.

c. Particle ejection 3. Nucleus absorbs neutron and spits into two similarly sized parts.

d. Radiative capture 4. Nucleus is struck by a neutron and emits a single neutron.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04 [1.0 point]

What effect does Doppler Broadening for U-238 have on neutrons in a critical core?

a. More Scattering

b. More Absorption

c. Increase the Reproduction Factor

d. Increase the Resonance Escape Probability QUESTION A.05 [1.0 point]

A reactor contains a neutron source that produces 10,000 neutrons/second. The reactor has a keff = 0.80. What is the stable total neutron production rate in the reactor?

a. 20,000 neutrons/second

b. 50,000 neutrons/second

c. 80,000 neutrons/second

d. 200,000 neutrons/second QUESTION A.06 [1.0 point]

Which one of the following terms describes the total amount of reactivity added by inserting or withdrawing a control rod from a reference height to any other rod height?

a. Integral Rod Worth

b. Differential Rod Worth

c. Shutdown Reactivity

d. Reference Margin Reactivity QUESTION A.07 [1.0 point]

Which ONE of the following conditions describes a critical reactor?

a. k = 1; k/k = 1

b. k = 0; k/k = 0

c. k = 0; k/k = 1

d. k = 1; k/k = 0

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.08 [1.0 point]

What is eff?

a. The fraction of all fission neutrons that are born as delayed neutrons

b. The fraction of all delayed neutrons that reach thermal energy

c. The time required for the reactor to change by power by a factor of e

d. The fractional change in neutron population per generation QUESTION A.09 [1.0 point]

Which ONE is correct about SUBCRITICAL MULTIPLICATION? As the reactor approaches criticality, the ___________.

a. M approaches one

b. keff approaches zero

c. 1/M approaches zero

d. approaches infinity QUESTION A.10 [1.0 point]

Which ONE of the following is the stable reactor period which will result in a power rise from 1%

to 100% in one minute?

a. 6 seconds

b. 13 seconds

c. 26 seconds

d. 44 seconds QUESTION A.11 [1.0 point]

A reactor is critical at 3 watts. A reactor operator mistakenly inserts a sample worth 1 positive beta into the reactor core. Which one best describes the reactor kinetics?

a. keff=1 and =0

b. keff >1 and =-eff

c. keff <1 and =1 beta

d. keff >1 and 0< < -eff

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.12 [1.0 point]

Which term below matches the definition, the number of neutrons passing through one cm2 of target material per second?

a. Neutron flux

b. Neutron density

c. Neutron population

d. Neutron impact potential QUESTION A.13 [1.0 point]

Delayed neutrons are born at _________ energies than prompt neutrons which leads to the effective delayed neutron fraction being __________ than the delayed neutron fraction.

a. lower, higher

b. lower, lower

c. higher, lower

d. higher, higher QUESTION A.14 [1.0 point]

Which ONE of the following atoms will cause a neutron to lose the most energy in an elastic collision?

a. Hydrogen-1

b. Oxygen-16

c. Argon-40

d. Uranium-238 QUESTION A.15 [1.0 point]

What is the half-life of a material with an original activity of 2400 cps, after 10 minutes an activity of 1757 cps?

a. 8 minutes

b. 22 minutes

c. 35 minutes

d. 41 minutes

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16 [1.0 point]

Which ONE of the following factors in the six factor formula is the MOST affected by the MODERATOR?

a. Fast fission factor

b. Reproduction factor

c. Thermal utilization factor

d. Resonance escape probability QUESTION A.17 [1.0 point]

Reactor A has a keff of 0.1 and Reactor B has a keff of 0.8. keff is increased by 0.1 for each reactor. The amount of reactivity added in reactor A is ________ in Reactor B for the same increment.

a. Less than

b. Same

c. Eight times

d. Thirty-six times QUESTION A.18 [1.0 point]

Which ONE of the following is the new keff of the reactor if, initially the reactor is subcritical with a shutdown margin of 0.526k/k and the addition of a reactor experiment increases the indicated count rate from 10 cps to 20 cps?

a. 0.639

b. 0.828

c. 0.975

d. 1.014 QUESTION A.19 [1.0 point]

Which ONE of the following statements best defines the reactor excess reactivity? The reactor excess reactivity is:

a. a measure of the additional fuel loaded to overcome fission product poisoning.

b. a measure of remaining control rod worth when the reactor is exactly critical.

c. the combined control rod negative reactivity worth required to keep the reactor shutdown.

d. The maximum reactivity by which the reactor can be shutdown with one control rod fully withdrawn.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.20 [1.0 point]

Which ONE of the following factors of the Six Factor Formula is MOST affected by removing the graphite reflector in the thermal column?

a. Thermal Utilization Factor (f)

b. Fast Non-Leakage Factor (Lt)

c. Resonance Escape Probability ()

d. Fast Fission Factor ()

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

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01 [1.0 point]

Which ONE of the following is the Limiting Condition of Operation objective to specify lowest acceptable level of performance, instrument set points, and the minimum number of operable components for the reactor control and safety systems?

a. Reactivity Limits

b. Control and Safety Systems

c. Limitations on Experiments

d. Radiation Monitoring, Control and Shielding QUESTION B.02 [1.0 point]

Which ONE of the following surveillances is a Channel Check?

a. Disconnecting a HV neutron flux channel to verify a reactor scram.

b. During performance of the daily checklist, you press the scram button to verify a scram on the safety system channel.

c. Adjustment of the Area Radiation Monitor to a specified setpoint from a dedicated check source.

d. Verification of the log channel performance requirements by observation.

QUESTION B.03 [1.0 point]

In accordance with Idaho State University (ISU) Emergency Plan which ONE of the following DOES NOT require the reactor operator shall order a building evacuation?

a. Bomb threat to the reactor

b. 10 mR/hr outside Room 20

c. 10 mR/hr outside Room 23

d. Airborne radioactive materials QUESTION B.04 [1.0 point]

A semiannual test of the nuclear instrument was performed. Which ONE of the following is the LATEST the test must be performed again without violation of the Technical Specifications?

a. 22 weeks

b. 30 weeks

c. 8 months

d. 12 months

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05 [1.0 point]

Approximately how far from a sample must a Radiation Area sign be posted if the irradiated sample has a half-life of 60 minutes with a dose rate of 1 rem/hr at 1 foot?

a. 6 feet

b. 9 feet

c. 14 feet

d. 32 feet QUESTION B.06 [1.0 point]

In accordance with 10 CFR 20.1301, what is the Total Effective Dose Equivalent (TEDE) in one year to individual members of the public?

a. 10 mrem

b. 100 mrem

c. 500 mrem

d. 1250 mrem QUESTION B.07 [1.0 point]

Per the ISU Emergency Plan, how frequent are operators required to receive emergency training and drills?

a. Monthly

b. Quarterly

c. Semi-Annual

d. Annually QUESTION B.08 [1.0 point]

10 CFR 50 allows the operator to deviate from Technical Specifications in order to ensure the health and safety of the public. What is the MINIMUM level of authorization needed to deviate from Technical Specifications?

a. Licensed Reactor Operator

b. Licensed Senior Reactor Operator

c. Reactor Supervisor

d. Reactor Administrator

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.09 [1.0 point]

Which 10 CFR part requires all applicants for an RO or SRO license submit Form 396 and 398 to the U.S. NRC before taking the examinations?

a. 19

b. 20

c. 50

d. 55 QUESTION B.10 [1.0 point]

How long will it take a 10 Curie source, with a half-life of 5 years, to decay to 1 Curie?

a. 6.3 years

b. 11.5 years

c. 16.6 years

d. 23.1 years QUESTION B.11 [1.0 point]

Which ONE of the following experiments listed below requires Double Encapsulation per ISU Technical Specifications?

a. An experiment containing liquid fissionable material

b. An experiment containing 22 grams of explosive material

c. An experiment containing a non-corrosive material to reactor components

d. An experiment, calculated upon failure to release an approximate total dose equivalent of 0.02 mSv for a period of two hours stating at the time, as a result of any airborne pathway QUESTION B.12 [1.0 point]

A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 350 mrem/hr with the window open and 100 mrem/hr with the window closed. What is the gamma dose rate?

a. 100 mrem/hr

b. 250 mrem/hr

c. 350 mrem/hr

d. 450 mrem/hr

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13 [1.0 point]

What is your dose rate at 1 foot away from the source, if you are receiving 300 mR/hr at 3 feet away from the source?

a. 2.2 R/hr

b. 2.7 R/hr

c. 3.5 R/hr

d. 3.9 R/hr QUESTION B.14 [1.0 point]

Which ONE of the following radioactive isotopes is commonly produced in the ISU AGN-201 experimental ports?

a. U-233

b. U-235

c. Pu-94

d. Au-198 QUESTION B. 15 [1.0 point]

An area of radiation reads 640 mRem/hr. How long can you stay before exceeding your annual federal limit?

a. 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

b. 7.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

c. 10.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

d. 12.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months QUESTION B.16 [1.0 point]

Per ISU MP#1, the reason for allowing only one control rod to be removed and disassembled during maintenance is to ___________.

a. Prevent inadvertent criticality

b. Limit the exposure to personnel

c. Prevent the inadvertent interchange of parts

d. Limit the number of maintenance operations being performed concurrently

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.17 [1.0 point]

During ISU emergency recovery operations to restore the facility to a safe status, who must assess the existing radiation and contamination levels?

a. Any two individuals on the team

b. Reactor Supervisor and Reactor Administrator

c. Director of Emergency Operations and Pocatello Fire Chief

d. Radiation Safety & Dose Assessment Coordinator and Recovery Operations Coordinator QUESTION B.18 [2.0 points, 0.50 each]

Match the 10 CFR Part 55 requirements listed in Column A for an actively licensed operator with the correct time period from Column B (Answers in Column B may be used once, more than once or not at all).

Column A Column B

a. License Expiration 1. One Year

b. Medical Examination 2. Two Years

c. Requalification Written Examination 3. Four Years

d. Requalification Operating Test 4. Six Years QUESTION B.19 [1.0 point]

Which ONE of the following surveillance requirements is the frequency for the calibration of all portable and installed radiation survey instrumentation?

a. Monthly

b. Quarterly

c. Annually

d. Biennual

(***** End of Category B *****)

Category C: Facility and Radiation Monitoring Systems QUESTION C.01 [2.0 points, 0.50 each]

Match the readings in Column A with their respective Technical Specification responses listed in Column B (Assume the reactor is in operation. Items in Column B may be used once, more than once or not at all).

Column A Column B

a. Reactor Period 9 seconds 1. Rod Interlock

b. Nuclear Safety Channel #2 = 1 x 10-13 2. Scram

c. Nuclear Safety Channel #1 = 0.4 cps 3. Normal Operation

d. Inserting both Safety Rods Simultaneously QUESTION C.02 [1.0 point]

ISU experiment plan #4, allows flux determination by two methods. What are the two approved methods?

a. Ion Chamber or Uranium Foils

b. Indium Foils or Scintillation Counter

c. Solid State Detector with Boron Convertor or Nickel Foils

d. Gold Wire or Fission Counter QUESTION C.03 [1.0 point]

In accordance with ISU Experiment #5, Reactor Power Calibration, it compares reactor power to which ONE of the following detector currents?

a. Channel #1

b. Channel #2

c. Channel #3

d. Radiation Channel QUESTION C.04 [1.0 point]

Which ONE of the following is the type of detector used for the Low Temperature Switch?

a. Bi-Metallic Thermal Switch

b. Resistance Temperature Detector

c. Type K, Chromel-Alumel Thermocouple

d. Type T, Copper Constantan Thermocouple

Category C: Facility and Radiation Monitoring Systems QUESTION C.05 [1.0 point]

Which ONE of the following supplies the Period information?

a. BF3 Geiger-Mueller

b. Nuclear Safety Channel #1

c. Nuclear Safety Channel #2

d. Nuclear Safety Channel #3 QUESTION C.06 [1.0 point]

Which ONE of the following individuals, by title, is required to be present during the opening or closing of the reactor core tank in accordance with ISU MP #2?

a. Reactor Operator

b. Senior Reactor Operator

c. Reactor Supervisor

d. Reactor Administrator QUESTION C.07 [1.0 point]

Which component contains water that shields operators from neutron radiation?

a. Glory Hole

b. Outer Steel Tank

c. Inner Polyethylene Tank

d. Graphite Neutron Column QUESTION C.08 [1.0 point]

Which ONE of the following is designed to retain all fission product gasses produced in the core?

a. Aluminum Core Tank

b. Aluminum Capsule housing the BF3 Detector for Nuclear Safety Channel #1

c. Outer Steel Tank

d. Graphite Reflector surrounding the Core

Category C: Facility and Radiation Monitoring Systems QUESTION C.09 [1.0 point]

Which ONE of the following methods is used to generate control rod position indication?

a. Direct output from the rod drive DC motor

b. Output of a synchro-generator linked to the rod drive DC motor

c. Change in voltage due to movement of a lead screw linked to the rod

d. Changing current due to closing of multiple magnetic switches located the length of the rod QUESTION C.10 [1.0 point]

OP #1 requires a 400V verification of the following Channels EXCEPT __________.

a. ALL Channels

b. Channel #1

c. Channel #2

d. Channel #3 QUESTION C.11 [1.0 point]

Which ONE of the following materials comprises the tank that contains the core and part of the reflector?

a. Boron

b. Graphite

c. Concrete

d. Aluminum QUESTION C.12 [1.0 point]

Which ONE of the following uses a float switch?

a. Earthquake Seismic monitor

b. Shield Tank Water Level Monitor

c. Glory Hole Differential Monitor

d. Control Room Pressure monitor

Category C: Facility and Radiation Monitoring Systems QUESTION C.13 [1.0 point]

What design feature ensures that the thermal fuse melts before the rest of the reactor core?

a. Fuse has double the density of fuel as the rest of the core

b. Moderator has half the density polyethylene to aid in thermalizing neutrons

c. Moderator has twice the density of polyethylene to aid in thermalizing neutrons

d. Fuse has double the ratio of Uranium-235 to Uranium-236 atoms as the rest of the core QUESTION C.14 [1.0 point]

The Glory Hole produces the majority of the facilitys _________.

a. Argon-41

b. Boron-10

c. Cadmium-56

d. Not applicable QUESTION C.15 [1.0 point]

What type of material is used as the moderator in the fuse and core?

a. Graphite and Lead

b. Water and Cadmium

c. Polystyrene and Polyethylene

d. Beryllium and Aluminum QUESTION C.16 [1.0 point]

Safety Control Rod #1 uses which ONE of the following drives?

a. Reversible DC motor, through lead screw assemblies, controlled by switches at the control console

b. Valve mechanisms designed to insert or withdraw dependent on the prescribed input settings

c. Synchro-generator requiring physical movement to the desired result

d. Rack and pinion gear system controlled by direct analog input

Category C: Facility and Radiation Monitoring Systems QUESTION C.17 [1.0 point]

As a minimum, how long must the reactor be shutdown and secured prior to opening the reactor core tank?

a. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

b. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

c. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

d. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months QUESTION C.18 [2.0 points, 0.25 each]

In the following diagram, match the item in Column B with the appropriate location in Column A.

(Answers may be used once, more than once or not at all).

Column A Column B

a. 1. Fuel Disks

b. 2. Glory Hole

c. 3. Core Tank

d. 4. Core Tank Cover

e. 5. Thermal Fuse

f. 6. Core Support Assembly

g. 7. Graphite Reflector

h. 8. Control and Safety Rod Thimbles

Category C: Facility and Radiation Monitoring Systems

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

((***** END OF EXAM *****))

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Sec 4.5 A.02 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Table 2.5 A.03 Answer: a. 3 b. 4 c. 2 d. 1

Reference:

Standard NRC Question A.04 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.1 A.05 Answer: b

Reference:

SCR = S / (1-keff); N = 10,000 / (1 - 0.8) = 50,000 Neutrons/second; DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 4, EO 1.2, page 4 A.06 Answer: b

Reference:

Standard NRC question A.07 Answer: d

Reference:

LaMarsh, Introduction to Nuclear Engineering, 3rd Edition, Section 4.3 A.08 Answer: a

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 2 A.09 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Table 5.5 A.10 Answer: b

Reference:

P=Poet/T T = t/ln(P/Po); T = 60 / ln(100); T = 13 seconds A.11 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 4.2 A.12 Answer: a

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 3, Section 2.2

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.13 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.2.4 A.14 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 2.5.3 A.15 Answer: b

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 1; A=Aoe-T A.16 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.1 A.17 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.3, page 3-21.

Reactor A = (keff1 - keff2) / (keff1

keff2); (0.2 - 0.1) / (0.2

0.1) = 5 k/k Reactor B = (keff1 - keff2) / (keff1

keff2); (0.9 - 0.8) / (0.9

0.8) = 0.139 k/k A.18 Answer: b

Reference:

SDM= 1 - keff/keff, keff = 1/1+0.526; keff = 0.6553; CR1 / CR2 = (1- keff2) / (1 - keff1) 10/20 = (1 - keff2) / (1 - 0.6553), (0.5) x (0.3447) = (1 - keff2), keff2 = 1- (0.5)(0.3447) =

0.82765 A.19 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 6.2 A.20 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.1

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.1 Answer: b

Reference:

ISU TS 3.2 B.2 Answer: d

Reference:

NRC standard question B.3 Answer: a

Reference:

ISU Emergency Plan, Appendix C.1 and C.6 B.4 Answer: b

Reference:

ISU TS 1.30 B.5 Answer: c

Reference:

Radiation Area >5mrem/hour; 1000 mrem (1) (2) = 5 mrem/hr (d) (2); D = 14.1 ft.

B.6 Answer: b

Reference:

10 CFR 20.1301 B.7 Answer: d

Reference:

ISU Emergency Plan, 10.2.3 B.8 Answer: b

Reference:

10 CFR 50.54(y)

B.9 Answer: d

Reference:

10 CFR 55 B.10 Answer: c

Reference:

A =Aoe-t; 1 Ci = 10Ci e-t; ln (1/10) = -ln2/5 yr * -> -2.30/-0.138 = 16.6 years B.11 Answer: a

Reference:

ISU TS 3.3 B.12 Answer: a

Reference:

NRC Standard question, basic radiation instrumentation B.13 Answer: b

Reference:

I1D12=I2D22 300mR/hr@(3ft)2=I2@(1ft)2 2700 mR/hr or 2.7 R/hr

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.14 Answer: d

Reference:

10CFR20.1003, byproduct material is radioactive material made radioactive by the process of using special nuclear material B.15 Answer: b

Reference:

5000 mRem / 640 mRem/hr = 7.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months B.16 Answer: c

Reference:

ISU MP#1 B.17 Answer: d

Reference:

ISU Emergency Plan 9.0 B.18 Answer: a. 4, b. 2, c. 2, d. 1

Reference:

10 CFR 55 B.19 Answer: b

Reference:

ISU Technical Specification,

Category C: Facility and Radiation Monitoring Systems C.01 Answer: a. 3, b. 2, c. 2, d. 1

Reference:

ISU TS 3.2 C.02 Answer: d

Reference:

ISU Experiment #4 C.03 Answer: c

Reference:

ISU Experiment #5 C.04 Answer: a

Reference:

ISU SAR 4.3.4, Page 70 C.05 Answer: c

Reference:

ISU SAR 4.3.2, Page 62 C.06 Answer: c

Reference:

ISU MP #2 C.07 Answer: b

Reference:

ISU SAR 4.1, Page 40 C.08 Answer: a

Reference:

ISU SAR 5.8 C.09 Answer: b

Reference:

ISU SAR 4.3-1 C.10 Answer: b

Reference:

ISU OP#1, II.C, II.D, II.E C.11 Answer: d

Reference:

ISU SAR 4.2, Page 42 C.12 Answer: b

Reference:

ISU SAR 4.3.4 C.13 Answer: a

Reference:

ISU SAR 4.2, Table 4.2-1

Category C: Facility and Radiation Monitoring Systems C.14 Answer: a

Reference:

ISU SAR 5.4 C.15 Answer: c

Reference:

ISU SAR 4.2, Table 4.2-1 C.16 Answer: a

Reference:

ISU SAR 4.3.1, Page 54 C.17 Answer: a

Reference:

ISU SAR 4.2 C.18 Answer: a. 4, b. 7, c. 1, d. 2, e. 5, f. 3, g. 8, h. 6

Reference:

ISU SAR Figure 4.2-3, Page 44

ML18291A965

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SUBJECT:

Dear Dr. Dunzik-Gougar:

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