ML18152A741

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Examination Report No. 50-284/OL-18-01, Idaho State University
ML18152A741
Person / Time
Site: Idaho State University, 05573200, 05573202
Issue date: 05/31/2018
From: Anthony Mendiola
Research and Test Reactors Oversight Projects Branch
To: Dunzik-Gougar M
Idaho State University
Ferguson A
Shared Package
ML18110A312 List:
References
50-284/18-01 50-284/OL-18
Download: ML18152A741 (33)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 31, 2018 Dr. Mary Lou Dunzik-Gougar, Reactor Administrator And Professor and Chair of Nuclear Engineering 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-18-01, IDAHO STATE UNIVERSITY

Dear Dr. Dunzik-Gougar:

During the week of May 7, 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-18-01
2. Facility Comments with NRC Resolution
3. Written Examination cc w/o enclosures: See next page

ML18152A741 NRR-079 OFFICE NRR/DLR/PROB/CE NRR/DIRS/IOLB/OLA NRR/DLR/PROB/BC NAME MDeSouza CJRandiki AMendiola DATE 05/11/2018 05/25/2018 05/31/2018 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 83209-8060 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-18-01 FACILITY DOCKET NO.: 50-284 FACILITY LICENSE NO.: R-110 FACILITY: AGN-201 EXAMINATION DATES: May 7-10, 2018 SUBMITTED BY: __________/RA/______________ 05/22/2018 Michele DeSouza, Chief Examiner Date

SUMMARY

During the week of May 7, 2018, the NRC administered an operator licensing examination to two Senior Reactor Operator Upgrade (SRO-U) candidates and three Reactor Operator (RO) candidates. The SRO Upgrade and one RO candidates passed all applicable portions of the examination(s). One RO candidate failed Category A and one RO candidate failed Category B of the written examination.

REPORT DETAILS

1. Examiner: Michele DeSouza, Chief Examiner, NRC
2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/2 0/0 1/2 Operating Tests 3/0 2/0 5/0 Overall 1/2 2/0 3/2

3. Exit Meeting:

Michele C. DeSouza, Chief Examiner, NRC Jay Kunze, Retired Dean of Engineering and former Reactor Administrator, Idaho State University Mary Lou Dunzik-Gouger, Reactor Administrator, Idaho State University Maxwell J. Daniels, Reactor Supervisor, Idaho State University Matthew Beatty, Training Instructor/SRO, Idaho State University Per discussion with the facility, prior to administration of the examination, adjustments to the written examination 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: ISU REACTOR TYPE: AGN-201 DATE ADMINISTERED: 05/09/2018 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 ___ (0.5 each)

A18 a b c d ___

A19 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

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 the direct source of DELAYED neutrons in the fission process?

a. Fission of U-235
b. Absorption of U-235
c. Spontaneous fission of the fission products
d. Decay of the fission product daughters QUESTION A.02 [1.0 point]

Which of the following statements illustrates a characteristic of Subcritical Multiplication?

a. The number of source neutrons decreases for each generation
b. The number of fission neutrons remains constant for each generation
c. As k-eff approaches unity (1), for the same increase in k-eff, a greater increase in neutron population occurs
d. Number of neutrons gained per generation gets larger for each succeeding generation QUESTION A.03 [1.0 point, 0.25 each]

Match the term in Column A with its correct definition in Column B.

Column A Column B

a. Prompt Neutron 1. Neutron in equilibrium with its surroundings
b. Fast Neutron 2. Neutron born directly from fission
c. Thermal Neutron 3. Neutron born due to decay of a fission product
d. Delayed Neutron 4. Neutron at an energy level greater than its surroundings QUESTION A.04 [1.0 point]

Two common FISSION PRODUCTS that have especially large neutron cross sections and play a significant role in reactor physics are Sm-149 and _________.

a. Nitrogen-16
b. Argon-41
c. Iodine-131
d. Xenon-135

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.05 [1.0 point]

Which ONE of the following is the definition of k-eff, effective neutron multiplication factor?

a. absorption / (production + leakage)
b. (production + leakage) / absorption
c. production / (absorption + leakage)
d. (absorption + leakage) / production QUESTION A.06 [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 QUESTION A.07 [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.08 [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

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.09 [1.0 point]

Which factor, in the six-factor formula, is represented by the following ratio?

  1. of neutrons that reach thermal energy total # of neutrons before thermalization
a. Fast fission factor
b. Reproduction factor
c. Thermal utilization factor
d. Resonance escape probability QUESTION A.10 [1.0 point]

A reactor is critical at 0.1 mW, you are raising reactor power, and doubling time is 30 seconds.

What is the reactor power 1 minute later?

a. 0.4 mW
b. 0.6 mW
c. 0.8 mW
d. 1.2 mW QUESTION A.11 [1.0 point]

A reactor is on a CONSTANT positive period. Which ONE of the following power changes will take the SHORTEST time to complete?

a. 5% power - from 1% to 6% power
b. 10% power - from 10% to 20% power
c. 15% power - from 20% to 35% power
d. 20% power - from 40% to 60% power 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

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13 [1.0 point]

Which ONE of the following identifies how prompt neutrons are produced?

a. High energy photon pair production
b. Fission fragment decay
c. Directly from fission
d. Installed source QUESTION A.14 [1.0 point]

What is the average number of neutrons produced from every fission of Uranium-235 with thermal neutrons?

a. 2.42 neutrons
b. 2.66 neutrons
c. 2.81 neutrons
d. 2.93 neutrons 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 QUESTION A.16 [1.0 point]

Which ONE of the following best describes the difference between reflectors and moderators?

a. Reflectors decrease core leakage while moderators thermalize neutrons
b. Reflectors thermalize neutrons while moderators decrease core leakage
c. Reflectors decrease thermal leakage while moderators decrease fast leakage
d. Reflectors shield against neutrons while moderators decrease core leakage

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.17 [2.0 points, 0.5 each]

Given a mother isotope of 35Br87 identify each of the daughter isotopes as a result of: , +, -,

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

a. 33As 83
b. 34Se 87
c. 35Br 86
d. 36Kr 87 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 determines keff? keff is k times________.

a. Fast fission factor
b. Reproduction factor
c. Resonance escape probability
d. Total non-leakage probability

(***** 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 for Operation objective?

a. To assure that automatic protective action is initiated to prevent a safety limit from being exceeded.
b. To assure that the integrity of the fuel material is maintained and all fission products are retained in the core matrix.
c. To assure that the reactor can startup at all times.
d. To specify lowest acceptable level of performance, instrument set points, and the minimum number of operable components for the reactor control and safety systems.

QUESTION B.02 [1.0 point]

What type of radiation detector is preferred for finding area contamination?

a. Ionization Chamber
b. Proportional Counter
c. Geiger-Mueller
d. Scintillation detector QUESTION B.03 [1.0 point]

Idaho State University (ISU) Emergency Plan requires the reactor operator shall order a building evacuation for the following EXCEPT__________.

a. 10 mR/hr outside Room 20
b. 10 mR/hr outside Room 23
c. Bomb threat to the reactor
d. Airborne radioactive materials QUESTION B.04 [1.0 point]

What is the minimum number of hours the reactor be secured prior to opening the ISU core tank?

a. 12
b. 16
c. 18
d. 24

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

Which ONE of the following items will ALLOW a Reactor Operator to continue to operate the reactor? (Assume today is the three year anniversary of receiving your RO license)

a. Performed one startup over the past year
b. Last physical examination was three years ago
c. Two hours of console operation performed in the last quarter
d. Written exam administered by Reactor Supervisor was 10 months ago QUESTION B.06 [1.0 point]

Which ONE of the following federal regulations establish procedures and criteria for the issuance of licenses to Reactor Operators and Senior Reactor Operators?

a. 10 CFR 19
b. 10 CFR 20
c. 10 CFR 50
d. 10 CFR 55 QUESTION B.07 [1.0 point]

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

a. Quarterly
b. Semi-Annual
c. Annually
d. Biennial QUESTION B.08 [1.0 point]

Which ONE of the below listed procedures shall be approved as a MINIMUM by the Reactor Administrator EXCEPT?

a. Implementation of the Security Plan and Emergency Plan
b. Radiation Safety Protection for all reactor related personnel
c. Preventative or corrective maintenance which could affect the safety of the reactor
d. Temporary procedures that does not involve an unreviewed safety question

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

Which ONE of the following surveillances is classified as a Channel Test?

a. During performance of the daily checklist, you compare the prestart readings of the radiation area monitors to the previous day readings
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 wide range linear channel in accordance with recent data collected during a reactor power calibration
d. You expose a detector to a check source to verify that it responds QUESTION B.10 [1.0 point]

A radiation survey of an area reveals a general radiation reading of 10 mRem/hr. However, a small section of pipe (point source) reads 100 mRem/hr at one foot. Which ONE of the following is the posting requirement for the area, in accordance with 10CFR20? (2.54cm=1inch)

a. CAUTION - RADIATION AREA
b. CAUTION - HIGH RADIATION AREA
c. CAUTION - RADIOACTIVE MATERIAL
d. CAUTION - AIRBORNE RADIOACTIVITY AREA QUESTION B.11 [1.0 point]

Which ONE of the following experiments listed below requires Double Encapsulation per Idaho State University 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

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.12 [1.0 point]

Which ONE of the following locations is NOT an area where the Emergency Notification Rosters are required to be posted?

a. Reactor Laboratory, Room 20
b. Nuclear Engineering Laboratory Entrance, Room 14
c. Graduate Student Office, Room 19
d. Subcritical Assembly Laboratory Room 23 QUESTION B.13 [1.0 point]

What is your dose rate at 1 foot away from the source, if you are receiving 250 mR/hr at 3 feet away from the source?

a. 2.25 R/hr
b. 2.85 R/hr
c. 3.05 R/hr
d. 3.25 R/hr QUESTION B.14 [1.0 point]

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

a. Gold - 198
b. Uranium - 233
c. Uranium - 235
d. Plutonium - 239 QUESTION B. 15 [1.0 point]

An area of radiation reads 460 mRem/hr. How long can you stay before exceeding your annual federal limit?

a. 10.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />
b. 14.64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br />
c. 15.23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />
d. 16.11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16 [1.0 point]

Per ISU Technical Specification, which ONE of the following is NOT a requirement for records to be maintained for the life of the facility?

a. Gaseous and liquid radioactive effluents released to the environs
b. Radiation exposures for all personnel
c. Rod worth measurements and other reactivity measurements
d. Fuel inventories and fuel transfers 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. Reactor Supervisor and Reactor Administrator
b. Director of Emergency Operations and Pocatello Fire Chief
c. Radiation Safety & Dose Assessment Coordinator and Recovery Operations Coordinator
d. Any two individuals on the team QUESTION B.18 [2.0 points, 0.50 each]

Match the positions in Column A with their corresponding responsibilities in Column B (Answers used only once).

Column A Column B

a. Reactor Operator 1. Qualified to activate manual scram and initiate emergency procedures
b. Authorized Operator 2. Responsible for the manipulation of the reactor controls
c. Certified Operator 3. Responsible for the preparation and enforcement of administrative controls
d. Reactor Supervisor 4. Authorized to operate under direction

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19 [1.0 point]

Which ONE of the following surveillance requirements is the frequency for the calibration of the radiation monitoring instrumentation?

a. Monthly
b. Annually
c. Every two years
d. Prior to start-up

(***** 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 6 seconds 1. Normal Operation
b. Nuclear Safety Channel #2 = 1 x 10-13 2. Rod Interlock
c. Nuclear Safety Channel #1 = 0.4 cps 3. Scram
d. Inserting both Safety Rods Simultaneously QUESTION C.02 [1.0 point]

Which ONE of the following supplies the Period information?

a. BF3 Geiger-Mueller Chamber
b. Nuclear Safety Channel #3
c. Nuclear Safety Channel #2
d. Nuclear Safety Channel #1 QUESTION C.03 [1.0 point]

Which ONE of the following will result in opening the interlock bus according to ISU Technical Specifications?

a. Electrical continuity of the seismic sensor is maintained
b. Bi-metallic thermal switch indicates a temperature of 15.6
c. The shield tank water level is 9.3 inches from the top of the manhole cover
d. The Channel #1 calibration switch is in the ZERO position QUESTION C.04 [1.0 point]

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

a. Resistance Temperature Detector
b. Bi-Metallic Thermal Switch
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]

ISU Technical Specifications requires fuel elements be stored in a safe array where the keff is less than _______.

a. 0.6
b. 0.7
c. 0.8
d. 0.9 QUESTION C.06 [1.0 point]

Which ONE of the following makes up the largest source of radiation when the reactor is shutdown and secured?

a. Nuclear Fission
b. Opening the Core Tank
c. Radioactive Check Sources
d. Radioactive Fission Products QUESTION C.07 [1.0 point]

Which facility uses water to shield against fast neutrons?

a. Inner Polyethylene Tank
b. Outer Steel Tank
c. Glory Hole
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]

Which ONE of the following Channels does NOT require 400V verification during OP#1?

a. Channel #1
b. Channel #2
c. Channel #3
d. Radiation Channel QUESTION C.11 [1.0 point]

The core and part of the reflector are contained in the ________ tank.

a. Boron
b. Concrete
c. Aluminum
d. Graphite QUESTION C.12 [1.0 point]

Which ONE of the following is the switch used for the shield tank water level?

a. Resistance
b. Bi-metallic thermal
c. Float
d. Differential pressure

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. Moderator has half the density polyethylene to aid in thermalizing neutrons
b. Fuse has double the density of fuel as the rest of the core
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]

Where is the majority of the facilitys Ar-41 produced?

a. Glory hole
b. Reactor bay
c. Core water
d. Rods and fuel QUESTION C.15 [1.0 point]

The fuse and core use what type of material as the moderator?

a. Beryllium and Aluminum
b. Polystyrene and Polyethylene
c. Water and Cadmium
d. Graphite and Lead QUESTION C.16 [1.0 point]

Which ONE of the following is the drives for the coarse and fine control rods?

a. Synchro-generator requiring physical movement to the desired result
b. Valve mechanisms designed to insert or withdraw dependent on the prescribed input settings
c. Reversible DC motor, through lead screw assemblies, controlled by switches at the control console
d. Rack and pinion gear system controlled by direct analog input

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

Which ONE of the following is NOT the correct response in relation to the fuel rods?

a. Increase moderation while inserting rods into the core
b. Increase reactivity while inserting rods into the core
c. Decrease reactivity while withdrawing rods from the core
d. Decrease moderation while inserting rods into the core 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. Control and Safety Rod Thimbles
b. 2. Core Tank
c. 3. Thermal Fuse
d. 4. Glory Hole
e. 5. Graphite Reflector
f. 6. Fuel Disks
g. 7. Core Support Assembly
h. 8. Core Tank Cover

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:

Lamarsh, Introduction to Nuclear Engineering, 3rd Edition, page 87 A.02 Answer: c

Reference:

Standard NRC Reactor Theory Question A.03 Answer: a. 2 b. 4 c. 1 d. 3

Reference:

Standard NRC Question A.04 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 8.1, Page 8-1 A.05 Answer: c

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 3 A.06 Answer: d

Reference:

LaMarsh, Introduction to Nuclear Engineering, 3rd Edition, Section 4.3 A.07 Answer: a

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 2 A.08 Answer: b

Reference:

Standard NRC question A.09 Answer: d

Reference:

LaMarsh, Introduction to Nuclear Engineering, 3rd Edition, Section 6.5, page 287 A.10 Answer: a

Reference:

P=Poet/T A.11 Answer: d

Reference:

P=Poet/Tt=T*ln(P/Po) assume constant period=1 The smallest ratio of P/Po is the shortest time to complete 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: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.2 A.14 Answer: a

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2 A.15 Answer: b

Reference:

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

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 5.4 A.17 Answer: a. b. + c. n d. -

Reference:

Standard NRC question 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 - 0.95), (0.5) x (0.05) = (1 - keff2), keff2 = 1- (0.5)(0.05) =

0.82765 A.19 Answer: d

Reference:

DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, page 9

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

Reference:

ISU TS 3.2 B.2 Answer: c

Reference:

NRC standard question B.3 Answer: c

Reference:

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

Reference:

ISU Maintenance Procedure #2, Prerequisites and Safety B.5 Answer: d

Reference:

10CFR55.53 and ISU Requal Plan B.6 Answer: d

Reference:

10CFR55.1(a)

B.7 Answer: c

Reference:

ISU Emergency Plan, 10.2.3 B.8 Answer: d

Reference:

ISU TS, 6.6, Page 26 B.9 Answer: b

Reference:

ISU TS definitions B.10 Answer: b

Reference:

10 CFR 20.1003; S=So(ro/r)2, therefore for a point source, 100 mrem/hr at 1 ft =

103.23mrem/hr at 30 cm B.11 Answer: a

Reference:

ISU Reactor Operator Requalification Program and 10 CFR 55.53 B.12 Answer: c

Reference:

ISU Emergency Plan 7.1.2 B.13 Answer: a

Reference:

I1D12=I2D22 250mR/hr@(3ft)2=I2@(1ft)2 2250 mR/hr or 2.25 R/hr

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

Reference:

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

Reference:

5000 mRem / 460 mRem/hr = 10.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br /> B.16 Answer: c

Reference:

ISU TS 6.10 B.17 Answer: c

Reference:

ISU Emergency Plan 9.0 B.18 Answer: a. 2, b. 4, c. 1, d. 3

Reference:

ISU Technical Specification, 6.1.4, 6.1.5, 6.1.6, and 6.1.7 B.19 Answer: b

Reference:

ISU Technical Specification, 4.2.i

C.01 Answer: a. 1, b. 3, c. 3, d. 2

Reference:

ISU TS 3.2 C.02 Answer: c

Reference:

ISU SAR 4.3.2, Page 62 C.03 Answer: d

Reference:

ISU SAR 4.3.4, Page 70 C.04 Answer: b

Reference:

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

Reference:

ISU TS 5.2 C.06 Answer: d

Reference:

ISU SAR 5.7 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: a

Reference:

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

Reference:

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

Reference:

ISU SAR 4.3.4 C.13 Answer: b

Reference:

ISU SAR 4.2, Table 4.2-1

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

Reference:

ISU SAR 5.4 C.15 Answer: b

Reference:

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

Reference:

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

Reference:

ISU SAR 4.2, Page 42 C.18 Answer: a. 8, b. 5, c. 6, d. 4, e. 3, f. 2, g. 1, h. 7

Reference:

ISU SAR Figure 4.2-3, Page 44

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