ML25160A274
| ML25160A274 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 08/20/2025 |
| From: | Michael Brown NRC/NRR/DANU/UNPO |
| To: | Sanford M Univ of Missouri - Columbia |
| References | |
| 50-186/25-02 50-186/OL-25 | |
| Download: ML25160A274 (36) | |
Text
Matthew Sanford, Executive Director University of Missouri-Columbia Research Reactor Center 1513 Research Park Drive Columbia, MO 65211
SUBJECT:
EXAMINATION REPORT NO. 50-186/OL-25-02, UNIVERSITY OF MISSOURI -
COLUMBIA
Dear Matthew Sanford:
During the week of July 28, 2025, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Missouri-Columbia research reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.
In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records 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. 50-186
Enclosures:
- 1. Examination Report No. 50-186/OL-25-02
- 2. Written examination cc: w/enclosures to GovDelivery Subscribers August 20, 2025 Signed by Brown, Tony on 08/20/25
ML25160A274 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza (ABeasten for)
NJones TBrown DATE 8/20/2025 8/20/2025 8/20/2025 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-186/OL-25-02 FACILITY DOCKET NO.:
50-186 FACILITY LICENSE NO.:
R-103 FACILITY:
University of Missouri - Columbia EXAMINATION DATES:
Week of July 28, 2025 SUBMITTED BY:
SUMMARY
During the week of July 28, 2025, the NRC administered operator licensing examinations to one Reactor Operator (RO) and three Senior Reactor Operator - Upgrade (SRO-U) candidates. All RO and SROU candidates passed all applicable portions of the examination and tests.
REPORT DETAILS 1.
Examiner:
Michele C. DeSouza, Chief Examiner, NRC 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 N/A 1/0 Operating Tests 1/0 3/0 4/0 Overall 1/0 3/0 4/0 3.
Exit Meeting:
Matthew Sanford, Executive Director Deborah Farnsworth, MURR Senior Director-Reactor Operations Thomas Forland, Associate Director Regulatory Affairs Jake Nichols, MURR Environmental Health & Safety Manager Russ Gibson, MURR Interim Reactor Manager Rob Hudson, MURR Assistant Reactor Manager-Training Michele C. DeSouza, Chief Examiner, NRC 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 8/4/2025 Michele C. DeSouza, Chief Examiner Date University of Missouri Research Reactor Operator Licensing Examination Week of July 28, 2025
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
University of Missouri Research Reactor REACTOR TYPE:
Tank DATE ADMINISTERED: July 29, 2025 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% or greater in each category and a 70% or greater overall are required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.
CATEGORY VALUE
% OF TOTAL CANDIDATE'S SCORE
% OF CATEGORY VALUE CATEGORY 20.00 33.0 A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTERISTICS 20.00 33.0 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.0 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
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 as well as a grade of 70 percent or greater overall.
12.
There is a time limit of three (3) hours for completion of the examination.
Category A: Reactor Theory, Thermodynamics, & Facility Operating Characteristics A N S W E R S H E E T Multiple Choice (Circle your choice)
If you change your answer, write your final selection on the blank line. If there is a conflict between what is circled and what is written on the blank line, the blank 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 ___
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)
If you change your answer, write your final selection on the blank line. If there is a conflict between what is circled and what is written on the blank line, the blank will be taken as the final answer.
B01 a b c d ___
B02 a ______ b ______ c ______ d ______
(0.25 each)
B03 a b c d ___
B04 a ______ b ______ c ______ d ______
(0.50 each)
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 ___
B19 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)
If you change your answer, write your final selection on the blank line. If there is a conflict between what is circled and what is written on the blank line, the blank 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 ___
C20 a b c d ___
(***** END OF CATEGORY C *****)
(********** END OF 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
T UA H
m T
c m
Q P
sec 10 1
4
2 1
1 1
2 1
eff eff K
CR K
CR
eff SUR 06 26
te P
P 0
eff K
S S
1
2 2
1 1
CR CR
0 1
P P
1 2
1 1
CR CR K
M eff
)
(
0 10 t
SUR P
P 2
1 1
1 eff eff K
K M
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
2 2
2 2
1 1
d DR d
DR
t e
DR DR
0
1 2
1 2
2 2
Peak Peak
2 6
R n
E Ci DR
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01
[1.00 point]
Which ONE of the following statements BEST describes inelastic scattering?
- a. A neutron collides with a nucleus and recoils with the same kinetic energy as prior to the collision.
- b. A neutron collides with a nucleus and is absorbed, with the nucleus emitting a charged particle.
c.
A neutron collides with a nucleus and is absorbed to form a compound nucleus, with the nucleus releasing a gamma ray.
- d. A neutron collides with a nucleus and is absorbed to form a compound nucleus, with the nucleus emitting a gamma ray and the neutron with a lower kinetic energy.
QUESTION A.02
[1.00 point]
Which ONE of the following describes the reason Xenon-135 and Samarium-149 have an impact on reactor physics?
- a. They both cause an increase in thermal flux due to burnup.
- b. They both cause excess positive reactivity in the core.
c.
They both have small thermal neutron absorption cross-sections.
- d. They both have large thermal absorption cross-sections which cause large removal of neutrons from the reactor.
QUESTION A.03
[1.00 point]
Which ONE of the following is the primary mechanism for transferring heat through the cladding of a fuel rod?
- a. Conduction b.
Convection c.
Transformation d.
Mass Transfer
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04
[1.00 point]
Which ONE of the following conditions will DECREASE the core excess reactivity of a reactor?
a.
Fuel depletion b.
Burnout of a burnable poison c.
It is a process where a neutron is absorbed by the nucleus and the nucleus releases a proton and a beta particle in order to return to its original energy.
d.
It is a process where a neutron collides with a nucleus imparting significant energy, resulting in the nucleus splitting and releasing more neutrons as a result.
QUESTION A.05
[1.00 point]
Which ONE of the following elements has the LARGEST Mean Free Path?
a.
Boron ( = 105.2 cm-1) b.
Tungsten ( = 1.21 cm-1) c.
Plutonium ( = 31.1 cm-1) d.
Titanium ( = 0.323 cm-1)
QUESTION A.06
[1.0 point]
Which ONE of the following is defined as the balance between production of neutrons and their absorption in the core for which core leakage can be neglected?
a.
Utilization Factor b.
Reproduction Factor c.
Infinite Multiplication Factor d.
Effective Multiplication Factor QUESTION A.07
[1.00 point]
If Kinf = 1.44, determine Keff for a reactor with a probability of fast non-leakage of 0.77 and a probability of thermal non-leakage of 0.92.
a.
1.01 b.
1.02 c.
1.20 d.
1.26
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.08
[1.00 point]
Which ONE of the following is the meaning of any point on a differential rod worth curve?
a.
The negative reactivity added as the rod is inserted.
b.
The cumulative area under the differential curve starting from the bottom of the core.
c.
The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn.
d.
The amount of reactivity that one unit (e.g. on inch, one percent) of rod motion would insert at that position in the core.
QUESTION A.09
[1.00 point]
Which ONE of the following answers lists the factors from the Six Factor Formula that are MOST affected during short transients of reactor operation?
a.
Reproduction Factor b.
Resonance Escape Probability c.
Fast Non-Leakage Probability d.
Thermal Non-Leakage Probability QUESTION A.10
[1.00 point]
Which ONE of the following best describes the reason that, following a reactor scram from full licensed power, indicated reactor power does NOT immediately decay to zero?
a.
In-core nuclear instrumentation lags the prompt drop.
b.
Core neutron population is sustained by spontaneous fission of Uranium-235.
c.
Core neutron population is sustained by the delayed neutron precursors.
d.
Core neutron population is sustained by neutrons from the installed neutron source.
QUESTION A.11
[1.00 point]
Which ONE of the following changes does NOT require a movement of control rods to maintain constant reactor power?
a.
Nitrogen-16 formation b.
Xenon-135 buildup c.
Uranium-235 burnup d.
Pool water temperature decrease
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.12
[1.00 point]
What is the reactor period if = 0.007 and = 0.005?
a.
4.02 seconds b.
8.04 seconds c.
20.5 seconds d.
100.7 seconds QUESTION A.13
[1.00 point]
Which ONE of the following is the multiplication factor? Given: source strength is 5000 neutrons per second (N/sec) and it produces the stable neutron count rate of 20,000 N/sec.
a.
0.70 b.
0.75 c.
0.85 d.
0.90 QUESTION A.14
[1.00 point]
Which ONE of the following is a characteristic of an effective core reflector?
a.
A low thermal conductivity.
b.
A small crystal expansion structure.
c.
A low resistance to radiation damage.
d.
A high scattering to absorption cross section ratio.
QUESTION A.15
[1.00 point]
If reactor power is at 65 W and $1.15 worth of reactivity is added resulting in a 8 second period, what will reactor power be after 1 minute?
a.
106.3 kW b.
117.5 kW c.
198.1 kW d.
225.4 kW
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16
[1.00 point]
Which ONE of the following isotopes will absorb more neutrons when it interacts with neutrons?
a.
Hydrogen-1 b.
Argon-40 c.
Boron-10
- d. Uranium-235 QUESTION A.17
[1.00 point]
Which ONE of the following is the definition of Reactivity?
a.
Rate of change of reactor power in neutron per second b.
Fractional change in neutron population per generation c.
Number of neutrons by which neutron population changes per generation d.
Change in the number of neutrons per second that causes a fission event QUESTION A.18
[1.00 point]
Which ONE of the following is the largest amount of energy per fission event appears in the form of kinetic energy?
a.
Gammas b.
Fast neutrons c.
Prompt and delayed neutrons d.
Fission fragments
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19
[1.00 point]
Which ONE of the following statements BEST describes the damage fast neutrons do to core structures?
a.
Fast neutrons undergo absorption reactions which lead to the activation and eventual decay of the core structure.
b.
Fast neutrons displace metal atoms in core structures leading to brittleness, swelling, and a loss of strength.
c.
Fast neutrons undergo elastic scattering with the metal in the core structure, ionizing the material and leading to eventual degradation.
d.
Fast neutrons have one of the highest radiation weighting factors and cause long term damage through the high amounts of imparted energy.
QUESTION A.20
[1.00 point]
Shown below is a trace of reactor period as a function of time. Between points D and E reactor power is:
a.
constant.
b.
continually decreasing.
c.
continually increasing.
d.
increasing, then constant.
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01
[1.00 point]
In accordance with MURR Operator Requalification Program which ONE of the following is NOT a requirement for a licensed reactor operators annual on the job training?
a.
Annual review of abnormal and emergency procedures b.
Participate in annual Health Physics training c.
Participate in two refueling evolutions d.
Perform five reactivity changes annually QUESTION B.02
[1.00 point, 0.25 each]
During normal reactor operation, match the system status requirement in Column B with the containment system in Column A. Answers may be used once, more than once, or not at all.
Column A Column B a.
Backup doors
- 1. Open b.
Ventilation Isolation
- 2. Closed c.
Hot Exhaust Valves d.
Personnel Airlock Doors QUESTION B.03
[1.00 point]
In accordance with the MURR EP-RO-004, Emergency Procedure, Fire, which ONE of the following events is NOT a required immediate action?
a.
Initiate a facility evacuation.
b.
Close all fire and smoke doors.
c.
Activate the Facility Emergency Organization.
d.
Coordinate with the Incident Commander and Command Post.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04
[2.00 points, 0.50 each]
In accordance with 10 CFR 20, match the radiation readings from Column A with its corresponding radiation area classification in Column B. Assume all distances at 30cm unless specified. Answers may be used once, more than once, or not at all.
Column A Column B a.
1 mR/hour
- 1. Unrestricted Area b.
150 R/hour
- 2. Radiation Area c.
10 mR/hour
- 3. High Radiation Area d.
550 Rad in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> @ 1 meter
- 4. Very High Radiation Area QUESTION B.05
[1.00 point]
In the absence of the beryllium reflector, why would replacing the graphite reflector with water raise the reactor core critical mass by more than 20%?
a.
The absorption cross section of water is too high.
b.
Graphite scatters neutrons while water absorbs neutrons.
c.
Graphite can be fabricated in solid form while water must be contained.
d.
Given the nuclear properties, graphite is a better reflector than water.
QUESTION B.06
[1.00 point]
While working on an experiment, you receive the following radiation doses: 100 mrem (),
25 mrem (), and 5 mrem (thermal neutrons). Which ONE of the following is your total dose?
a.
115 mrem b.
130 mrem c.
150 mrem d.
175 mrem
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07
[1.00 point]
In accordance with the MURR Technical Specifications, which ONE of the following experiments would be allowed in the core for irradiation?
a.
A singly encapsulated experiment containing 15g of Francium powder and 15g of Sodium powder.
b.
An experiment that contains 20 mg of TNT in a container rated to withstand the pressure from a detonation of 25 mg of TNT.
c.
A fueled experiment that upon irradiation would contain 250 mCi of I-131 and 600 mCi of I-133.
d.
An experiment containing Plutonium that if breeched would result in an uptake dose of 50 rem to the lungs.
QUESTION B.08
[1.00 point]
Which ONE of the following scenarios would result in an occupational worker violating their 10 CFR 20 annual dose limits?
a.
Handling a sample releasing a beta radiation dose of 2 rem/hr for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
b.
Accidentally ingesting contaminated water, that results in a dose to the liver of 55 rem.
c.
Accidentally inhaling some radioactive powder that results in an uptake of 15 rem to the lungs.
d.
Handling a fueled experiment that emits a beta radiation dose of 50 rem/hr on contact for 3 minutes.
QUESTION B.09
[1.00 point]
In accordance with MURR Emergency Procedures, which ONE of the following defines the Emergency Planning Zone (EPZ)?
a.
100 meter radius from the MURR exhaust stack and outside the site boundary.
b.
As deemed necessary by the Emergency Director with input from the Health Physicist.
c.
Dictated by the Facility Director after consulting with the Nuclear Regulatory Commission and within the walls of the MURR building.
d.
150 meter radius from the MURR exhaust stack and completely bounded within the site boundary.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10
[1.00 point]
A radiation survey instrument was used to measure an irradiated experiment. The results were 200 mR/hr with the window open and 140 mR/hr with the window closed. Not accounting for any Beta correction factor or instrument efficiencies, what is the estimated Beta dose?
a.
40 mR/hour b.
60 mR/hour c.
140 mR/hour d.
200 mR/hour QUESTION B.11
[1.00 point]
How much reactivity should be added in order to increase reactor power from 800 W to 400 kW? Assuming = 0.007.
a.
0.00345 b.
0.00428 c.
0.00592 d.
0.00699 QUESTION B.12
[1.00 point]
Which one of the following has the ability to minimize any reactivity effects from experiments in the beam ports, bulk pool or graphite reflector?
a.
Beryllium reflector b.
Rod run in interlock c.
Regulating control blade d.
Pressurizer low level scram
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13
[1.00 point]
In accordance with 10 CFR 50.59, which ONE of the following scenarios would NOT require an evaluation?
a.
Amending the reactor power calibration procedure to correct spelling mistakes.
b.
Running an experiment in the pneumatic transfer system to be filled with gaseous nitrogen.
c.
Changing a Technical Specifications surveillance requirement from monthly to quarterly.
d.
Adding a step to the control blade reactivity worth measurement procedure to allow the operator to try a new method for determining reactivity worths.
QUESTION B.14
[1.00 point]
In accordance with the MURR Emergency Plan, which ONE of the following is NOT classified as a Notification of Unusual Event?
a.
A prolonged fire b.
Civil disturbance directed toward the reactor c.
Earthquake landing in the parking lot d.
Significant radioactive materials release as a result of an experiment failure QUESTION B.15
[1.00 point]
In accordance with the MURR Technical Specifications, ALL of the following are semiannual requirements EXCEPT:
a.
Ability of the emergency power generator to assume the emergency electrical loads.
b.
Channel calibration of the radiation monitoring instrumentation.
c.
Total reactivity worth of each shim blade.
d.
Operability of the primary coolant relief valve systems.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16
[1.00 point]
Which ONE of the following Emergency Classifications would apply given the following conditions? Fuel damage caused a release or airborne radioactive materials of 110,000 Air Effluent Concentration (AEC) averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a.
Unclassified b.
Notification of Unusual Event c.
Alert d.
Site Area Emergency QUESTION B. 17
[1.00 point]
According to the MURR Emergency Plan, which ONE of the following is the action term associated with the implementing procedure for this emergency class and may include evacuation of a room or small part of the MURR facility?
a.
Subsequent Actions b.
Corrective Actions c.
Assessment Actions d.
Specific Protective Actions QUESTION B.18
[1.00 point]
Which ONE of the following MURR Technical Specification surveillances is NOT a monthly requirement?
a.
Operability verification of the ventilation isolation and bypass valves.
b.
Pool water radioactivity measurements.
c.
Thermal power verification of power range indications.
d.
Primary coolant pH and conductivity measurements.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19
[1.00 point]
In accordance with MURR Operator Requalification Program, what is the minimum number of supervised operation if you have a lapse in your active license status?
a.
2 b.
4 c.
6 d.
10
(***** END OF CATEGORY B *****)
Category C: Facility and Radiation Monitoring Systems QUESTION C.01
[1.00 point]
In accordance with MURR Technical Specifications, which ONE of the following would NOT cause a reactor scram in Mode I?
a.
Pool coolant flow is 750 gpm b.
Pressurizer high pressure is 100 psia c.
Differential pressure across reflector is 5 psi d.
Pressurizer low water level is 15 inches QUESTION C.02
[1.00 point]
Which ONE of the following devices provides the shim blade console indication full in/full out?
a.
Digital encoder b.
Limit switches c.
10-turn potentiometer d.
Lead screw assembly QUESTION C.03
[1.00 point]
In the main air system, which ONE of the following allows to interrupt the service to any part of the laboratory building without disrupting service to the remainder of the building?
a.
Isolation valves b.
Reduced pressure valves c.
Flow containment devices d.
Electrical indication restrictors
Category C: Facility and Radiation Monitoring Systems QUESTION C.04
[1.00 point]
Which ONE of the following BEST describes how a Compensated Ion Chamber (CIC) operates?
a.
The CIC has only one chamber coated with Boron-10 for (n, ) reaction.
b.
The CIC has only one chamber coated with Uranium-235 for fission reaction.
c.
The CIC has two chambers, both can sense gamma rays but only one is coated with Boron-10 for (n, ) reaction.
d.
The CIC has two chambers, one is coated with Uranium-235 for fission reaction and the other is coated with Boron-10 for (n, ) reaction.
QUESTION C.05
[1.00 point]
Without the beryllium reflector, what would be the impact on the reactor?
a.
Remain subcritical b.
Instantly become critical c.
Achieve supercritical within 2 minutes d.
Would require removal of 8 fuel elements to prevent boiling QUESTION C.06
[1.00 point]
If, during fuel inspections fuel is found to be defective, what is the reason for removal from service?
a.
Removal ensures new fuel may be immediately ordered.
b.
To assure proper heat removal requirements and prevent the release of radioactivity into the primary coolant system.
c.
To provide the necessary increased reactivity to maintain the required level of coolant flow where the damaged fuel was located.
d.
To prevent pressurization from the damaged fuel expanding into the surrounding fuel elements.
Category C: Facility and Radiation Monitoring Systems QUESTION C.07
[1.00 point]
In accordance with MURR Technical Specifications and SAR, which ONE of the following is NOT a safety feature?
a.
The design of the scram safety circuit.
b.
The fuel material type and fuel cladding.
c.
The reactor containment system.
d.
The reactor anti-siphon system.
QUESTION C.08
[1.00 point]
In the event of a loss of normal power and actuation of the emergency electrical systems, which ONE of the following is NOT maintained?
a.
Containment doors b.
Personnel entry doors c.
Facility ventilation exhaust fans d.
Control blades QUESTION C.09
[1.00 point]
Which ONE of the following was NOT taken into consideration when designing reactor pool fuel storage system?
a.
Cooling b.
Shape c.
Shielding d.
Geometry QUESTION C.10
[1.00 point]
Which ONE of the following radionuclides was of greatest concern when designing the reactor containment system, monitored daily, and annual release amounts reported to the Nuclear Regulatory Commission?
a.
Xenon-133 b.
Cesium-137 c.
Argon-41 d.
Category C: Facility and Radiation Monitoring Systems QUESTION C.11
[1.00 point]
Which ONE of the following experimental facilities has a decoupling design feature that is considered an inherent safety feature that effectively assists the control blades in controlling reactor power?
a.
Beam ports b.
Thermal column c.
Center test hole (flux trap) d.
Bulk pool irradiation positions QUESTION C.12
[1.00 point]
Which ONE of the following Area Radiation Monitor Systems (ARMS) channels does NOT cause a building isolation?
a.
Room 114 b.
Air plenum 2 c.
Reactor bridge d.
Bridge ALARA QUESTION C.13
[1.00 point]
Which ONE of the following ventilation system features maintains reactor containment and laboratory buildings and prevents the spread of radioactive contamination such as airborne radioactive materials?
a.
Ensures a slightly positive pressure to clear the air from reactor-related areas through recombination.
b.
Maintained at a slightly negative pressure to push or contain the air within the reactor-related areas.
c.
Independent air balance in each area to isolate or restrict as appropriate.
d.
Dedicated ventilation hoods to effectively monitor and ensure the flow is maintained without regard to pressures.
Category C: Facility and Radiation Monitoring Systems QUESTION C.14
[1.00 point]
Which ONE of the following characteristics is true for ALL the control blades used at MURR?
a.
They are all Stainless Steel clad.
b.
The all have uniform lengths and diameters.
c.
They utilize mechanical device drive mechanisms that are constant speed.
d.
They occupy approximately 18° circular arc around the pressure vessel.
QUESTION C.15
[1.00 point]
Which ONE of the following conditions indicates a reactor pool tank leak?
a.
A sudden increase in the pool water temperature.
b.
An abnormally high water conductivity averaged over a month.
c.
An increase in the pressure of the primary cooling system.
d.
Having to add an abnormally large amount of makeup water in a week.
QUESTION C.16
[1.00 point]
Which ONE of the following devices ensures the reactor pool will not be completely drained when a large leak develops in the primary coolant piping system?
a.
Siphon breaks b.
Heat Exchanger c.
Primary coolant pump d.
Intermediate coolant backup system QUESTION C.17
[1.00 point]
Which ONE of the following actions would NOT impact the critical positions of the control rods?
a.
Movement of fuel into and out of the core.
b.
A decrease in the pool water temperature by 5° C.
c.
An increase in the negative pressure differential between the reactor bay and outside.
d.
Previous reactor runs in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the previous 5 days.
Category C: Facility and Radiation Monitoring Systems QUESTION C.18
[1.00 point]
Which ONE of the following statements is NOT accurate concerning the radiation monitors?
a.
The radiation monitors are isolated from each other such that the operation of one does not affect the operation of another.
b.
The emergency electrical power system provides a continuous supply of electrical power to the radiation monitors in the event of a loss of normal electrical power.
c.
The radiation monitors are powered by independent low voltage power supply and not subject to a single failure event.
d.
The radiation monitors are electrically coupled to ensure a failure or excess indication on one device results in the proper indication and response on all devices.
QUESTION C.19
[1.00 point]
Which ONE of the following air radiation monitoring channels contains a charcoal cartridge?
a.
Gas channel b.
Iodine channel c.
Particulate channel d.
Air plenum #1 channel QUESTION C.20
[1.00 point]
The MURR thermal column makeup is composed of which ONE of the following materials?
a.
Concrete and lead b.
Lead and stainless steel only c
Graphite, lead, and aluminum d.
Boron, lead, and stainless steel
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer:
d
Reference:
DOE Fundamentals Handbook, Volume 1, Module 1, p. 45 A.02 Answer:
d
Reference:
DOE Fundamentals Handbook, Volume 2, Module 3, p. 34 A.03 Answer:
a
Reference:
NRC Standard Question A.04 Answer:
a
Reference:
NRC Standard Question A.05 Answer:
d
Reference:
MFP = 1/
Boron ( = 105.2 cm-1) MFP = 1/105.2 = 0.0095 Tungsten ( = 1.21 cm-1) MFP = 1/1.21 = 0.8264 Plutonium ( = 31.1 cm-1) MFP = 1/31.1 = 0.0322 Titanium ( = 0.323 cm-1) MFP = 1/0.323 = 3.0960 A.06 Answer:
c
Reference:
DOE Fundamentals Handbook, Volume 2, Module 3, p. 2 A.07 Answer:
b
Reference:
Keff = Kinf*PFNL*PTNL = 1.44*0.77*0.92 = 1.02 A.08 Answer:
a
Reference:
Burn, Introduction to Nuclear Reactor Operators, Volume 2, p. 7-4, Example 7.2(b)
A.09 Answer:
b
Reference:
Burn, Introduction to Nuclear Reactor Operators, Volume 2, p. 3-16 A.10 Answer:
c
Reference:
Burn, Introduction to Nuclear Reactor Operators, Volume 2, p. 3-7 A.11 Answer:
a
Reference:
Burn, Introduction to Nuclear Reactor Operators, Volume 2, p. 7-17, Problem 7.7.4
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.12 Answer:
a
Reference:
=
+
= 1 104 0.005 + 0.007 0.005 0.1 0.005 T = 4.02 A.13 Answer:
b
Reference:
CR = S/(1-K) 20000 = 5000/(1 - K) = 1 -X = 5000/20000; K = 0.75 A.14 Answer:
d
Reference:
DOE Fundamentals Handbook, Vol. 2, Module 4, p. 25 A.15 Answer:
b
Reference:
= 0
= 65 60 8 = 117,522.757 117,5 A.16 Answer:
c
Reference:
Burn, Introduction to Nuclear Reactor Operators, Section 2.5.1, p. 2-38 to 2-43 Chart of the Nuclides A.17 Answer:
b
Reference:
DOE Fundamentals Handbook, Volume 2, Module 3, p. 18 A.18 Answer:
d
Reference:
Glasstone, Nuclear Reactor Engineering, Section 1.47 A.19 Answer:
b
Reference:
Burn, Introduction to Nuclear Reactor Operators, Vol. 1 p. 2-29 A.20 Answer:
c
Reference:
Burn, Introduction to Nuclear Reactor Operators, Figure 2.6, p. 2-39
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer:
c
Reference:
MURR Operator Requalification Program p. A-1 and A-2 B.02 Answer:
- a. 1-open; b. 1-open; c. 1-open; d. 2-closed
Reference:
MURR Reactor Operations Training, Containment Building, II, p. 3.1-1 B.03 Answer:
d
Reference:
MURR EP-RO-004, Emergency Procedure, Fire 1.0 B.04 Answer:
- a. 1-Unrestricted; b. 3-HRA; c. 2-RA; d. 4-VHRA
Reference:
10 CFR 20.1003 and 10 CFR 20.1004 B.05 Answer:
d
Reference:
MURR Reactor Operations Training p. 7.1-4 and NRC Standard Question B.06 Answer:
b
Reference:
100 mrem + 25 mrem + 5 mrem = 130 mrem B.07 Answer:
b
Reference:
MURR Technical Specifications 3.8 B.08 Answer:
b
Reference:
10 CFR 20.1201 B.09 Answer:
d
Reference:
MURR EP-RO-004, Emergency Procedure, Definitions 1.11 B.10 Answer:
b
Reference:
Window closed = dose only. Window open reads both and dose. Therefore, dose is window open dose less window closed dose. 200 - 140 = 60 mR/hour B.11 Answer:
d
Reference:
= 0 (1 )
( ) = 0 (1 )
() () = (0 ) (0 )
() (0 ) = () (0 )
=
() (0 )
( 0 )
=
(400000 0.007) (800 0.007)
(400000 (800 0.007))
= 0.006986
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.12 Answer:
a
Reference:
MURR Reactor Operations Training p. 7.1-3 B.13 Answer:
a
Reference:
10 CFR 50.59 B.14 Answer:
d
Reference:
MURR Emergency Plan, 3.2 and 3.3 B.15 Answer:
c
Reference:
MURR Technical Specifications 4 B.16 Answer:
c
Reference:
MURR REP-ROR-100, Reactor Emergency Procedures, High Stack Monitor Indications, p. 34 B.17 Answer:
d
Reference:
MURR Emergency Plan, 5.1.4 B.18 Answer:
c
Reference:
MURR Technical Specifications 4 B.19 Answer:
c
Reference:
MURR Operator Requalification Program, Active Status Log
(***** END OF CATEGORY B *****)
Category C: Facility and Radiation Monitoring Systems C.01 Answer:
c
Reference:
MURR Technical Specifications 3.2 C.02 Answer:
b
Reference:
MURR Reactor Operations Training p. 10.2.3 C.03 Answer:
a
Reference:
MURR Reactor Operations Training p.1.4-1 C.04 Answer:
c
Reference:
NRC Standard Question C.05 Answer:
a
Reference:
MURR Reactor Operations Training 7.1-2 C.06 Answer:
b
Reference:
MURR SAR 4.5.3, p. 4-43 C.07 Answer:
b
Reference:
MURR Technical Specifications 1.2.4 and MURR SAR 6, 6.2 and 6.3 C.08 Answer:
d
Reference:
b
Reference:
MURR SAR 4.3, 4.5.3, and 9.2 C.10 Answer:
c
Reference:
MURR SAR 1.4.2, p. 1-21 C.11 Answer:
c
Reference:
MURR SAR 7.2.1 and 10.1 C.12 Answer:
a
Reference:
MURR Reactor Operations Training, Reactor Isolation & Facility Evacuation, p.
3.4-1
Category C: Facility and Radiation Monitoring Systems C.13 Answer:
b
Reference:
MURR SAR 11.1.5.2, p. 11-50 C.14 Answer:
c
Reference:
d
Reference:
NRC Standard Question C.16 Answer:
a
Reference:
MURR SAR 6.3.8, p. 6-20 C.17 Answer:
c
Reference:
NRC Standard Question C.18 Answer:
d
Reference:
MURR SAR 7.8.2, p. 7-57 C.19 Answer:
b
Reference:
MURR Reactor Operations Training, p. 9.3-2 C.20 Answer:
c
Reference:
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)