ML25233A250
| ML25233A250 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 01/21/2026 |
| From: | Michael Brown NRC/NRR/DANU/UNPO |
| To: | Joel Jenkins Texas A&M Univ |
| References | |
| 50-128/26-01 50-128/OL-26 | |
| Download: ML25233A250 (0) | |
Text
Mr. Jere Jenkins, Director Nuclear Science Center Texas A&M Engineering Experiment Station 1095 Nuclear Science Road, MS 3575 College Station, TX 77843-3575
SUBJECT:
EXAMINATION REPORT NO. 50-128/OL-26-01, TEXAS A&M UNIVERSITY
Dear Mr. Jenkins:
During the week of January 5, 2026, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Texas A&M Engineering Experiment Station. 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 component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website 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 Michele DeSouza at 301-415-0747 or via email at Michele.DeSouza@nrc.gov.
Sincerely, Tony Brown, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-128
Enclosures:
- 1. Examination Report No. 50-128/OL-26-01
- 2. Written examination cc: w/enclosures to GovDelivery Subscribers January 21, 2026 Signed by Brown, Tony on 01/21/26
ML25233A250 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TBrown DATE 1/21/2026 1/21/2026 1/21/2026 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-128/OL-26-01 FACILITY DOCKET NO.:
50-128 FACILITY LICENSE NO.:
R-83 FACILITY:
Texas A&M Engineering Experiment Station EXAMINATION DATES:
Week of January 5, 2026 SUBMITTED BY:
SUMMARY
During the week of January 5, 2026, the NRC administered operator licensing examinations to two Reactor Operator (RO), two Senior Reactor Operator-Upgrade (SROU), and one SRO-Instant (SROI) candidates. The candidates passed all applicable portions of the examinations.
REPORT DETAILS 1.
Examiner:
Michele C. DeSouza, Chief Examiner, NRC 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 1/0 3/0 Operating Tests 2/0 3/0 5/0 Overall 2/0 3/0 5/0 3.
Exit Meeting:
Michele C. DeSouza, NRC, Chief Examiner Jere Jenkins, TEES, Director Richard C. Kurwitz, TEES, Interim Associate Director Prior to administration of the written examination, based on facility comments, adjustments were accepted. Comments provided corrections and additional clarity to questions/answers and identified where changes were appropriate based on current facility conditions.
Upon completion of all operator licensing examinations, 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.
Michele C. DeSouza 1/13/2026 Michele C. DeSouza, Chief Examiner Date Texas A&M Engineering Experiment Station Operator Licensing Examination Week of January 5, 2026
U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Texas A&M Engineering Experiment Station REACTOR TYPE:
TRIGA DATE ADMINISTERED:
01/08/2026 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 and 70% or greater overall 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
Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics A N S W E R S H E E T Multiple Choice (Circle your choice, or write on the line)
If you change your answer, write your selection on the line. Answers written on the line will be taken as the final answer.
A01 a b c d ___
A02 a b c d ___
A03 a b c d ___
A04 a b c d ___
A05 a b c d ___
A06 a __________ b __________ c __________ d __________ (0.25 each)
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 A N S W E R S H E E T Multiple Choice (Circle your choice, or write on the line)
If you change your answer, write your selection on the line. Answers written on the line will be taken as the final answer.
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 __________ (0.25 each)
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 ___
B19 a b c d ___
B20 a b c d ___
(***** END OF CATEGORY B *****)
Category C - Facility and Radiation Monitoring Systems A N S W E R S H E E T Multiple Choice (Circle your choice, or write on the line)
If you change your answer, write your selection on the line. Answers written on the line will be taken as the final answer.
C01 a b c d ___
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 ___
C19 A __________ B ___________ C __________ D __________
E __________ F __________ G __________ H __________
(0.29 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 and a 70 percent overall.
12.
There is a time limit of three (3) hours for completion of the examination.
EQUATION SHEET
=
+
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
2 2
max
P 1
sec 1.0
eff
te P
P 0
eff K
S S
1
sec 10 1
4
eff SUR 06 26
2 1
1 1
2 1
eff eff K
CR K
CR
2 2
1 1
CR CR 2
1 1
1 eff eff K
K M
1 2
1 1
CR CR K
M eff
)
(
0 10 t
SUR P
P
0 1
P P
eff eff K
K SDM
1
2 1
1 2
eff eff eff eff K
K K
K
693
.0 2
1 T
eff eff K
K 1
t e
DR DR
0
2 6
R n
E Ci DR 2
2 2
2 1
1 d
DR d
DR
1 2
1 2
2 2
Peak Peak
T UA H
m T
c m
Q P
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01
[1.00 point]
The reactor is critical and increasing in power. Power has increased from 10 watts to 800 watts in 90 seconds. How long, at this rate, will it take power to increase from 4 kW to 10 kW? Note:
Neglect any negative temperature coefficient.
a.
1.9 seconds b.
6.8 seconds c.
14 seconds d.
19 seconds QUESTION A.02
[1.00 point]
Which one of the following terms is associated with the definition, the resonance peaks of the neutron absorption cross section increase in width due to thermal motion of the nuclei?
a.
Mass Defect b.
Doppler Broadening c.
Spectrum Hardening d.
Moderator Negative Temperature Coefficient QUESTION A.03
[1.00 point]
Which ONE of the following is NOT a characteristic of an effective neutron moderator?
- a. low atomic density
- b. low neutron absorption cross section
- c. large neutron scattering cross section
- d. large neutron energy loss per collision QUESTION A.04
[1.00 point]
Which ONE of the following statements best defines reactor excess reactivity?
a.
A measure of the additional fuel loaded to overcome fission product poisoning.
b.
A measure of remaining control blade worth when the reactor is exactly critical.
c.
The combined control blade negative reactivity worth required to keep the reactor shutdown.
d.
The maximum reactivity by which the reactor can be shutdown with one control blade fully withdrawn.
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.05
[1.00 point]
Given a reactor period of 48 seconds, approximately how long will it take for power to quadruple?
a.
23 seconds b.
39 seconds c.
67 seconds d.
81 seconds QUESTION A.06
[1.00 point, 0.25 each]
Match the items in Column A with the isotopes in Column B.
The most important fission product poison is 135Xe. The process that shows how this isotope is formed and its decay is: (Answers used only once)
Column A Column B 1.
135 I 2.
135 Ba 3.
135 Te a
fission 11 0
1 +
b fission 6.7 0
1+ 135 fission 9.2 0
1+ c 2.36 d()
4.
135 Cs QUESTION A.07
[1.00 point]
Following a reactor scram, the period meter will indicate __________ because __________.
a.
Zero seconds; the reactor is subcritical, and reactor power is decreasing.
b.
-80 seconds; of the decay constant for the longest-lived neutron precursor.
c.
Slightly positive; the neutron source is providing detectable neutron count rate to keep the reactor slightly supercritical.
d.
-80 seconds; the fuel temperature coefficient adds positive reactivity as a result of the decrease in fuel temperature following a scram.
QUESTION A.08
[1.00 point]
Which ONE of the following describes the Integral Rod Worth?
- a. The reactivity change per unit movement of a rod.
- b. The total reactivity worth of the rod at a particular degree of withdrawal.
- c. The summation of all the reactivity worth of a rod up to the point of withdrawal.
- d. The plot of the slope of the change in reactivity over the change in rod position (/x).
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.09
[1.00 point]
Which ONE of the following decay chains correctly describes the production and removal of Xenon - 135 from the reactor?
- a. I135 - + Te135 - + Xe135 -+ Cs135 - + Ba135
- b. Te135 - + I135 - + Xe135 -+ Cs135 - + Ba135
- c. Te135 - + I135 - + Xe135 -+ Ba135 - + Cs135
- d. Te135 - + Cs135 - + Xe135 -+ I135 - + Ba135 QUESTION A.10
[1.00 point]
While bringing the reactor critical, which ONE of the following describes how a subcritical reactor responds to equal insertions of positive reactivity?
- a. Each reactivity insertion results in a larger increase in neutron flux resulting in a longer time to stabilize.
- b. Each reactivity insertion results in a smaller increase in neutron flux resulting in a shorter time to stabilize.
- c. Each reactivity insertion results in a larger increase in neutron flux resulting in a shorter time to stabilize.
- d. Each reactivity insertion results in a smaller increase in neutron flux resulting in a longer time to stabilize.
QUESTION A.11
[1.00 point]
Given the thermal neutron flux (Ø) is 1.0 x 1013 neutrons/cm2/second, and the macroscopic cross-section (f) for fission is 0.1 cm-1. Which ONE of the following is the fission rate?
- a. 1.0 x 1012 fissions/cm3/second
- b. 1.0 x 1014 fissions /cm3 /second
- c. 1.0 x 1014 fissions /cm2 /second
- d. 1.0 x 1012fissions /cm/second
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.12
[1.00 point]
During fission of Uranium-235, which ONE of the following accounts for the majority of energy released?
- a. Neutrinos
- b. Fission neutrons
- c. Capture gamma rays
- d. Fission fragments QUESTION A.13
[1.00 point]
Which ONE of the following BEST describes a supercritical reactor?
- a. Keff > 1 based on prompt neutrons alone
- b. Keff < 1 based on delayed and prompt neutrons
- c. Keff = 1 based on delayed neutrons alone
- d. Keff > 1 based on prompt and delayed neutrons QUESTION A.14
[1.00 point]
Which ONE of the following has a long-term effect on Keff but is of no consequence during short term and transient operation?
- a. Fuel burnup
- b. Increase in fuel temperature
- c. Increase in moderator temperature
[1.00 point]
The neutron microscopic cross-section for absorption a generally:
- a. increases as neutron energy increases
- b. decreases as neutron energy increases
- c. increases as neutron velocity increases
- d. decreases as target nucleus mass increases
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16
[1.00 point]
Which ONE of the following is the definition of Thermal Utilization Factor?
- a. The ratio of the number of fast neutrons absorbed in fuel to the number of fast neutrons absorbed in the reactor material.
- b. The ratio of the number of fast neutrons produced by thermal fission to the number of thermal neutrons absorbed in the fuel.
- c. The ratio of the number of thermal neutrons absorbed in the fuel to the number of thermal neutrons absorbed in all reactor materials.
- d. The ratio of the number of thermal neutrons produced by fission in a generation to the number of total neutrons produced by fission in the previous generation.
QUESTION A.17
[1.00 point]
How high will the reactor power get given the following: the lowest of the reactor high power scram set points is 120%, the scram delay time is 0.7 seconds, the reactor is operating at 100%
power prior to the scram, and the reactor period is positive 30 seconds?
- a. 101%
- b. 110%
- c. 123%
- d. 167%
QUESTION A.18
[1.00 point]
If (1 - eff )*Keff = 1, the reactor is:
a.
Subcritical b.
Critical c.
Supercritical d.
Prompt Critical QUESTION A.19
[1.00 point]
Which type of neutron interaction (light nuclei) is most important in MODERATING fast neutrons to thermal neutrons?
- a. Fission
- b. Neutron Capture
- c. Elastic Scattering
- d. Inelastic Scattering
Category A - Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.20
[1.00 point]
Which ONE of the following is the stable reactor period that will result in a power rise from 50%
to 100% power in 45 seconds?
- a. 21 seconds
- b. 34 seconds
- c. 56 seconds
- d. 65 seconds
(***** END OF CATEGORY A *****)
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01
[1.00 point]
In accordance with SOP D-2, Implementing Procedure for an Explosion involving reactor or Radioactive Material, which ONE of the following is NOT immediate action required by the Emergency Director in response?
a.
Notify a member of NSC management.
b.
Visually inspect to determine if shutdown is required.
c.
Account for personnel and direct them to a safe area.
d.
Health Physics monitor the area to determine if radioactivity is present.
QUESTION B.02
[1.00 point]
In accordance with 10 CFR 55.59 and TEES operator requalification plan, which ONE of the following is the operating test frequency requirement for maintaining an active operator license?
a.
Annually b.
Every 2 years c.
4 years d.
6 years QUESTION B.03
[1.00 point]
According to the TEES Emergency Plan, which ONE of the following is an action level associated with an Alert?
- a. Security threat affecting the reactor.
- b. Deep dose equivalent of 0.75 mSv.
- c. Committed effective dose equivalent of 15 mrem.
- d. Tornado observed adjacent to the parking lot.
QUESTION B.04
[1.00 point]
Reactor Operator works in a high radiation area for eight (8) hours a day. The dose rate in the area is 100 mrem/hour. Which ONE of the following is the MAXIMUM number of days in which Reactor Operator may perform his duties WITHOUT exceeding 10 CFR 20 limits?
- a. 5 days
- b. 6 days
- c. 7 days
- d. 12 days
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05
[1.00 point]
Which ONE of the following defines the term Radiation Area?
a.
Any area where access is limited for any reason.
b.
Any area to which access is limited for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials.
c.
Area where radiation exposure rates would result in a dose equivalent in excess of 5 mrem in one hour at 30 centimeters from the radiation source.
d.
Area where radiation exposure rates would result in a dose equivalent in excess of 1 mSv in one hour at 30 centimeters from the radiation source.
QUESTION B.06
[1.00 point, 0.25 each]
For each of the below, identify the required number of operable channels during steady state operating mode.
- a. High Power Level Scram
- b. Pool Water Temperature Scram
- c. Fuel Element Temperature Scram
- d. High Power Level Detector Power Supply Scram QUESTION B.07
[1.00 point]
In accordance with 10 CFR 55.53 and TEES requalification plan, what is the minimum number of hours required to reinstate an individuals license if the licensed operator could not meet their quarterly requirements?
- a. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- b. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
- c. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- d. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> QUESTION B.08
[1.00 point]
Which ONE of the following NRC Forms requires completion during initial licensure and every two years subsequently?
- a. NRC Form 3, Notice to Employees
- b. NRC Form 4, Cumulative Occupational Dose History
- c. NRC Form 396, Certification of Medical Examination by Facility Licensee
- d. NRC Form 398, Personal Qualification Statement - Licensee
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.09
[1.00 point]
Which ONE of the following is the definition of a Channel Check?
- a. The introduction of a signal into the channel for verification that is operable.
- b. A qualitative verification of acceptable performance by observation of channel behavior.
- c. The combination of sensor, line, amplifier, and output device which are connected for the purpose of measuring the value of a parameter.
- d. An adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures.
QUESTION B.10
[1.00 point]
Which ONE of the following changes would require submittal to the Nuclear Regulatory Commission for approval prior to implementation?
a.
Add a new limit to the pre-start checklist procedure.
b.
Replace the primary coolant pump with an identical one.
c.
Delete section 6.3, Radiation Safety listed in the TEES Technical Specifications.
d.
Add more responsibilities to the Radiation Safety Officer in the Radiation Safety Program.
QUESTION B.11
[1.00 point]
In accordance with 10 CFR 20, individual members of the public are limited to a dose in any unrestricted area from external sources, the dose in any one hour shall not exceed:
a.
2 mrem.
b.
10 mrem.
c.
50 mrem.
d.
500 mrem.
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.12
[1.00 point]
Which ONE of the following is NOT a requirement to prevent damage to the reactor or excessive release of radioactivity by limiting materials quantity and radioactive material inventory of the experiment in the event of an experiment failure?
a.
Corrosive materials shall be doubly encapsulated.
b.
Cryogenic liquids shall not be used in any experiment in the reactor pool.
c.
Explosive materials shall not be limited if the detonation pressure is less than half the design pressure of the container.
d.
The absolute value of the reactivity worth of each unsecured experiments which are in the reactor shall be less than $1.00.
QUESTION B.13
[1.00 point]
Which ONE of the following is the definition of a Curie?
a.
Number of radioactive atoms in the source.
b.
Number of nuclear disintegrations per unit time.
c.
Amount of energy emitted per unit time by the source.
d.
Amount of damage to soft body tissue per unit time.
QUESTION B.14
[1.00 point]
You are currently a licensed operator at TEES. Which ONE of the following would be a violation of 10 CFR Part 55.53 Conditions of licenses?
a.
Your last written examination was 18 months ago.
b.
Your last requalification operating test was 11 months ago.
c.
Last quarter you were on console as the licensed operator for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
d.
The new requalification program cycle started 18 months ago.
QUESTION B.15
[1.00 point]
During a reactor operation, a small fire occurs on the control room console. Which ONE of the following classes of fire extinguisher would most likely be used for this type of fire?
- a. Class A: Fires in ordinary combustibles, such as wood, paper, plastic, etc.
- b. Class B: Fires in flammable or combustible liquids, flammable gases, greases.
- c. Class C: Fires in live electrical equipment.
- d. Class D: Fires involving combustible metals such as magnesium.
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16
[1.00 point]
A radiation survey of an area reveals a general radiation reading of 1 mRem/hr. However, an irradiated experiment sample (point source) is brought into the area that reads 10 mRem/hr at 1 meter. Which ONE of the following is the required posting for the area, in accordance with 10 CFR Part 20?
- a. CAUTION - RADIATION AREA
- b. CAUTION - HIGH RADIATION AREA
- c. GRAVE DANGER - VERY HIGH RADIATION AREA
- d. CAUTION - AIRBORNE RADIOACTIVITY AREA QUESTION B.17
[1.00 point]
In accordance with TEES Technical Specifications, which ONE of the following is the correct frequency for visual inspection of the regulating rod and transient rod drive inspection?
a.
Monthly, annually b.
Every six months, every year c.
Every year, every year d.
Every two years, every six months QUESTION B.18
[1.00 point]
Per TEES Technical Specifications, the shutdown margin must be greater than __________.
- a. $0.25
- b. $0.40
- c. $0.50
- d. $0.75 QUESTION B.19
[1.00 point]
An experiment reading 40 rem/hr was removed from the reactor. Five hours later, it reads 8 rem/hr. What is the half-life of the experiment?
a.
1.23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> b.
2.15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> c.
3.43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> d.
5.98 hours0.00113 days <br />0.0272 hours <br />1.62037e-4 weeks <br />3.7289e-5 months <br />
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.20
[1.00 point]
In accordance with the TEES Emergency Plan, which ONE of the following defines the term Emergency Planning Zone?
a.
Area where the Emergency Coordinator can initiate emergency activities.
b.
The area where organizing is done to assure prompt and effective actions to protect the public in the event of an accident.
c.
Area where Emergency Coordinator has complete and total authority over all activities.
d.
An area where access is limited to protect individuals from exposure to radiation or radioactive materials in the event of an emergency.
(***** END OF CATEGORY B *****)
Category C - Facility and Radiation Monitoring Systems QUESTION C.01
[1.00 point]
In accordance with TEES Radiation Safety Program, quantities of special nuclear material of 0.5 grams or greater shall require which ONE of the following?
a.
Must be secured in unrestricted areas if they do not contain special identification.
b.
Must not be secured and should be used only with direct supervision by the Facility Director.
c.
Shall be located in restricted areas or under the control of authorized individuals only and must have a unique identification.
d.
Shall be labeled with the type of radioactive material, date, and individuals information that is responsible for securing the material.
QUESTION C.02
[1.00 point]
Which ONE of the following is NOT used as an external personal monitoring device?
- a. Bioassay
- b. Pocket Dosimeter
- c. Theromluminescent Dosimeter
- d. Optically Stimulated Luminescent Dosimeter QUESTION C.03
[1.00 point]
In accordance with the TEES SAR, which ONE of the following is used in combination with water as a neutron moderator?
- a. Lead
- b. Steel
- c. Bismuth
- d. Graphite QUESTION C.04
[1.00 point]
In automatic mode, which ONE of the following is correct?
- a. The log drawer provides power output to generate the signal to the preselected control rod.
- b. The source range indicates the direct connection to the predetermined power level.
- c. The wide range linear drawer provides the power level to the servo controller that generates the signal to drive the rod.
- d. The safety drawer indications generate the signal to the servo controller that is converted to a digital indication for the movement of the rod.
Category C - Facility and Radiation Monitoring Systems QUESTION C.05
[1.00 point]
The figure below depicts which ONE of the following nuclear instrumentation detectors?
a.
Fission Chamber b.
Geiger-Mueller Detector c.
Compensated Ion Chamber d.
Uncompensated Ion Chamber QUESTION C.06
[1.00 point]
Which ONE of the following is the complete system description of the Log Power Channel?
- a. Safety drawer and voltage readout power supply
- b. Compensated ion chamber, digital output, and direct feed indicator
- c. Wide range liner drawer, converter, and analog neutron rate counter
- d. Fission chamber, preamp, amplifier, log meter, and digital neutron rate counter QUESTION C.07
[1.00 point]
In accordance with the TEES SAR, building gas activity is monitored by __________ to document the release of __________.
a.
Compensated Ionization detector, Uranium-233
- c. Particulate Detector, all radioactive releases
- d. NaI Scintillation crystal detector, Argon-41
Category C - Facility and Radiation Monitoring Systems QUESTION C.08
[1.00 point]
Which ONE of the following is NOT a purpose of the demineralizer system?
- a. Convert city water into potable water.
- b. Maintain the pool surface free of dust and debri.
- c. Directs the water through the diffuser to ensure the clarity and purity is maintained.
- d. Provide the direct shielding needed to maintain the water within safe radiological levels.
QUESTION C.09
[1.00 point]
Which ONE of the following is correct? The Air Handler Shutdown button in the control room
- a. engages the cool air conditioning units to ensure proper interior temperatures.
- b. shifts the direction of the air through the ports designed to monitor the amount of radioactivity.
- c. isolates the building by closing the dampers and shutting off the air handlers.
- d. move air directionally opposite to decrease the amount of radioactivity and dilute for release.
QUESTION C.10
[1.00 point]
Which ONE of the following monitors receives its signal from the Compensated Ion Chamber (CIC)?
- a. Wide Range Linear Channel
- b. Power Range Log Monitor
- c. Source Range Monitor
- d. Pulse Range Channel QUESTION C.11
[1.00 point]
To prevent the spread of radioactive contamination such as airborne radioactive materials, the ventilation system maintains the reactor containment and laboratory buildings at which ONE of the following?
- a. Slightly positive pressure to clear the air from reactor-related areas
- b. Slightly negative pressure to push or contain the air within the reactor related areas
- c. Complete balance of pressure so all areas maintain their own air pressure in each area
- d. Pressure is not of concern; all areas release through ventilation hoods with monitoring
Category C - Facility and Radiation Monitoring Systems QUESTION C.12
[1.00 point]
In accordance with TEES Technical Specifications, which ONE of the following is the objective of the primary coolant purity system?
- a. Maximize the shielding and minimize monitoring requirements.
- b. Minimize the exterior residual exposures and maximize the density of the materials.
- c. Minimize corrosion of the fuel element cladding and minimize neutron activation.
- d. Maximize corrosion and direct it through the necessary components for filtration and proper handling.
QUESTION C.13
[1.00 point]
Which ONE of the following indications are provided from the Pulse Channel after firing a pulse?
- a. Peak power and Energy
- b. Peak power and 1 kW Interlock
- c. Energy and Fuel Temperature
- d. Percent power and Reactor period QUESTION C.14
[1.00 point]
Which ONE of the following is true about the operation of the Stack Isolation Dampers?
- a. Spring to close, air to open
- b. Motor to open, spring assisted motor to close
- c. Motor to close, air to open
- d. Motor to close, spring to open QUESTION C.15
[1.00 point]
In accordance with TEES Technical Specifications, if the pool level is __________, the reactor shall not be operated.
- a. below 1 foot from the reference operating level
- b. greater than 1 foot from the reference operating level
- c. below 3 feet from the reference operating level
- d. greater than 3 feet from the refence operating level
Category C - Facility and Radiation Monitoring Systems QUESTION C.16
[1.00 point]
Which ONE of the following is true concerning reviews and reports of limiting safety system setting violations?
- a. records to be retained for at least one certification cycle
- b. records to be retained for a minimum of five years or until the change is implemented to correct
- c. records to be retained for the lifetime of the reactor facility
- d. no requirement to maintain the records QUESTION C.17
[1.00 point]
Which ONE of the following is the material of the pneumatic system tube?
- a. Aluminum
- b. Cadmium lined steel
- c. Stainless steel
- d. Polyethylene QUESTION C.18
[1.00 point]
In accordance with TEES Radiation Safety Program, what is the MINIMUM calibration frequency of radiation safety instruments?
- a. Weekly
- b. Monthly
- c. Quarterly
- d. Annually
Category C - Facility and Radiation Monitoring Systems QUESTION C.19
[2.00 points, 0.50 each]
In the control rod diagram below, identify the parts (A-H) from this list (1-6):
Items in the list may be used once, more than once, or not at all.
- 1. Fuel
- 2. Void
- 3. Stainless Steel Plug
- 4. Borated Graphite
- 5. Zirconium Rod
- 6. Spacer A.
B.
C.
D.
E.
F.
G.
H.
(***** END OF CATEGORY C *****)
((********** END OF EXAMINATION **********))
Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics A.01 Answer:
d
==Reference:
==
P = P et/T 800 = 10*e (90 sec/T)
T = 20.54sec 10 kW = 4 kW*e (t/20.54) t = 19 seconds A.02 Answer:
b Reference: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory Volume 2, Module 3, page 4 A.03 Answer:
a
==Reference:
==
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 3, page 24 A.04 Answer:
b
==Reference:
==
Burn, Introduction to Nuclear Reactor Operations, Section 6.2 A.05 Answer:
c
==Reference:
==
P = P0et/T 4 = 1
- et/48 t = 48
- ln(4) t = 66.5 seconds -> 67 seconds A.06 Answer:
- a. 3; b. 1; c. 4; d. 2
==Reference:
==
Burn, Introduction to Nuclear Reactor Operations, Section 5.5 A.07 Answer:
b
==Reference:
==
DOE Fundamentals Handbook, Nuclear Physics & Reactor Theory, Volume 1, Module 2, page 7 A.08 Answer:
b
==Reference:
==
Burn, Introduction to Nuclear Reactor Operations, Section 3.4, page 3-32 A.09 Answer:
b Reference:
Burn, Introduction to Nuclear Reactor Operations, Figure 8-1, page 8-6 A.10 Answer:
a Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 5.3, page 5-12
Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics A.11 Answer:
a
==Reference:
==
Fission rate = thermal flux (Ø) x macroscopic cross-section. (f) = 1.0 x 10 13 neutrons/cm 2/second x 0.1 cm
-1 = 1.0 x 10 12 neutrons/cm 3/second Burn, Introduction to Nuclear Reactor Operations, Section 2.6.2 A.12 Answer:
d Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.2.1, Table 3.2, page 3-5 A.13 Answer:
d
==Reference:
==
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 1, Module 2, page 30 A.14 Answer:
a
==Reference:
==
Standard NRC question A.15 Answer:
b Reference: Burn, Introduction to Nuclear Reactor Operations, Section 2.5 A.16 Answer:
c Reference: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 3, page 4 A.17 Answer:
c
==Reference:
==
P/Po = 120%, T = 30 seconds, t = 0.7, P/Po = 120 e^0.7/30 = 123%
A.18 Answer:
d
==Reference:
==
Burn, Introduction to Nuclear Reactor Operations, Section 4.2 A.19 Answer:
c
==Reference:
==
LaMarsh, 3rd Ed., Section 3.6, page 345 A.20 Answer:
d
==Reference:
==
P = P0 et/T --> T= t/Ln(P/ P0 )
T= 45/Ln(100/50 ); T = 64.9 seconds or 65 seconds
(***** END OF CATEGORY A *****)
Category B - Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer:
b
==Reference:
==
TEES SOP D-2, Implementing Procedure for an Explosion Involving Reactor or Radioactive Material B.02 Answer:
a
==Reference:
==
10 CFR 55.59(a)(2) and TEES Operator Requalification Plan 5.0 B.03 Answer:
b
==Reference:
==
TEES Emergency Plan Appendix 2, Table I B.04 Answer:
b
==Reference:
==
10CFR20.1201(a)(1) [5000 mr x 1 hr x day] = 6.25 days = 6 days; 100 mr
- 8 hr B.05 Answer:
c
==Reference:
==
10 CFR 20.1003 B.06 Answer:
- a. 2; b. 1; c. 1; d. 2
==Reference:
==
TEES Technical Specifications Table 2a B.07 Answer:
c
==Reference:
==
10 CFR 55.53 and TEES Operator Requalification Plan 6.2 B.08 Answer:
c
==Reference:
==
10 CFR 55.21, 55.31 and NRC Form 396 B.09 Answer:
b
==Reference:
==
TEES Technical Specifications Definitions B.10 Answer:
c
==Reference:
==
TEES Technical Specifications changes require an amendment B.11 Answer:
a
==Reference:
==
10 CFR 20.1301 B.12 Answer:
c
==Reference:
==
TEES Technical Specifications 3.6 B.13 Answer:
b
==Reference:
==
Standard NRC question
Category B - Normal/Emergency Operating Procedures and Radiological Controls B.14 Answer:
c
==Reference:
==
10 CFR 55.53 B.15 Answer:
c
==Reference:
==
Standard NRC question B.16 Answer:
b
==Reference:
==
10 CFR 20.1003, 10 CFR 20.1902 (DR1)(D1)2=(DR2)(D2)2 (10 mrem/hr)(100 cm)2/(30 cm)2 = 111.1 mrem/hr B.17 Answer:
c
==Reference:
==
TEES Technical Specifications Section 4.2.3 B.18 Answer:
c
==Reference:
==
TEES Technical Specifications 3.1.3 B.19 Answer:
b Reference: DR = DR0, T1 2 =
0.693
DR = DR0 e-.693/T1/2 8 = 40 e-(.693)(5)/T1/2
- 0. = e-(.693)(5)/T1/2 ln(0.2) = ln(e-(.693)(5)/T1/2)
-1.609 = -3.465 / T1/2 T1/2 = -3.465 / -1.609 T1/2 = 2.15 hr B.20 Answer:
b
==Reference:
==
TEES Emergency Plan, Definitions
(***** END OF CATEGORY B *****)
C.01 Answer:
c
==Reference:
==
TEES NESC Radiation Safety Program 6.2 C.02 Answer:
a Reference:
TEES NESC Radiation Safety Program 6.3 C.03 Answer:
d Reference:
TEES NESC SAR 4.2.3 C.04 Answer:
c Reference:
TEES NESC SAR 7.2, page 106 C.05 Answer:
c Reference:
Standard NRC question C.06 Answer:
d
==Reference:
==
TEES NESC SAR 7.2.3, page 106 C.07 Answer:
d
==Reference:
==
TEES NESC SAR 11.1.1.1, page 144 C.08 Answer:
b
==Reference:
==
TEES NESC SAR 5.4, page 97 C.09 Answer:
c
==Reference:
==
TEES NESC SAR 6.2.1, page 103 C.10 Answer:
a
==Reference:
==
TEES NESC SAR 7.2.3.3, page 107 C.11 Answer:
b
==Reference:
==
TEES NESC SAR 9.1.2, page 127 C.12 Answer:
c
==Reference:
==
TEES Technical Specifications 3.8.1 C.13 Answer:
a
==Reference:
==
TEES NESC SAR 7.2.3.2, page 107 C.14
Answer:
b
==Reference:
==
Standard TEES question and knowledge C.15 Answer:
c
==Reference:
==
TEES Technical Specifications 3.8.2 C.16 Answer:
c
==Reference:
==
TEES Technical Specifications 6.8.3 C.17 Answer:
d
==Reference:
==
TEES NESC SAR 10.1.3, page 137 C.18 Answer:
d
==Reference:
==
TEES NESC Radiation Safety Program 7.3 C.19 Answer:
A. 2, Void; B. 3, Stainless Steel Plug; C. 4, Borated Graphite; D. 3, Stainless Steel Plug; E. 1, Fuel; F. 5, Zirconium Rod; G. 3. Stainless Steel Plug; H. 2, Void
==Reference:
==
TEES NESC SAR 4.2.2, Figure 4-10, page 29
(***** END OF CATEGORY C *****)
((********** END OF EXAMINATION **********))