ML25338A342
| ML25338A342 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia (R-103) |
| Issue date: | 02/09/2026 |
| From: | Michael Brown NRC/NRR/DANU/UNPO |
| To: | Sanford M Univ of Missouri - Columbia |
| References | |
| 50-186/OL-26-01 26-01 | |
| Download: ML25338A342 (0) | |
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-26-01, UNIVERSITY OF MISSOURI-COLUMBIA
Dear Matthew Sanford:
During the week of February 2, 2026, 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-26-01
- 2. Written examination cc: w/enclosures to GovDelivery Subscribers February 9, 2026 Signed by Brown, Tony on 02/09/26
ML25338A342 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TBrown DATE 2/9/2026 2/9/2026 2/9/2026 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-186/OL-26-01 FACILITY DOCKET NO.:
50-186 FACILITY LICENSE NO.:
R-103 FACILITY:
University of Missouri - Columbia Research Reactor EXAMINATION DATES:
Week of February 2, 2026 SUBMITTED BY:
SUMMARY
During the week of February 2, 2026, the NRC administered operator licensing examinations to two Reactor Operator (RO) candidates and one Senior Reactor Operator - Upgrade (SROU) candidate. All candidates passed all applicable portions of the examinations and tests.
REPORT DETAILS 1.
Examiner:
Michele DeSouza, Chief Examiner, NRC 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 0/0 2/0 Operating Tests 2/0 1/0 3/0 Overall 2/0 1/0 3/0 3.
Exit Meeting:
Michele DeSouza, Chief Examiner, NRC Rob Hudson, Assistant Reactor Manager, Training, MURR Austin Schnieders, Senior Manager Operations, MURR Shannon McCall, Assistant Reactor Manger, Compliance, MURR Deborah Farnsworth, Senior Director Reactor Operations & Reactor Manger, MURR Thomas Forland, Associate Director, Nuclear Regulatory Affairs, MURR Amber Gaddy, Senior Director, Regulatory Affairs, MURR Jake Nichols, Health Physics & Safety Manager, MURR Matthew Sanford, Reactor Facility Director, MURR Prior to administration, adjustments to the written exam were accepted based on facility comments. These 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 DeSouza February 4, 2026 Name, Chief Examiner Date University of Missouri - Columbia Research Reactor Operator Licensing Examination Week of February 2, 2026
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
MURR REACTOR TYPE:
Tank DATE ADMINISTERED:
February 4, 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 a 70% 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 and a 70 percent 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 ___
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 __________ (0.25 each)
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: Plant 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]
Given a source strength of 250 neutrons per second (N/sec) and a multiplication factor of 0.5, which ONE of the following is the expected stable neutron count rate?
a.
150 N/second b.
250 N/second c.
400 N/second d.
500 N/second QUESTION A.02
[1.00 point]
Which ONE of the following is the best description of 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 shield against neutrons while moderators decrease core leakage
- d. Reflectors decrease thermal leakage while moderators decrease fast leakage QUESTION A.03
[1.00 point]
Which ONE of the following statements correctly describes thermal neutrons?
- a. A neutron at resonant epithermal energy levels that causes fissions to occur in U-238 b.
A neutron that experiences no net change in energy after several collisions with atoms of the moderator c.
A neutron that experiences a linear decrease in energy as the temperature of the moderator increases d.
A neutron that experiences an increase in energy levels after collisions with larger atoms of the moderator
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04
[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.
39 seconds b.
56 seconds c.
65 seconds d.
77 seconds QUESTION A.05
[1.00 point]
Which ONE of the following isotopes is fissile?
a.
U-235 b.
Th-238 c.
Pu-238 d.
Cm-242 QUESTION A.06
[1.00 point]
During rod insertion of start-up, as the reactor approaches critical, which ONE of the following is the value of 1/M?
a.
Decreases toward one b.
Increases toward one c.
Increases toward infinity d.
Decreases toward zero QUESTION A.07
[1.00 point]
Which ONE of the following does the term prompt critical refer to?
a.
Reactivity insertion which is less than eff b.
Reactor which is critical by using both prompt and delayed neutrons c.
Instantaneous jump in power due to a removal of the control rods d.
Reactor which is critical by using only prompt neutrons
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.08
[1.00 point]
Five minutes after shutdown of the reactor, reactor power is 3 x 106 counts per minute (cpm).
Which ONE of the following is the count rate you would expect two minutes later?
a.
4 x 104 cpm
- b. 7 x 105 cpm c.
8 x 106 cpm d.
9 x 103 cpm QUESTION A.09
[1.00 point]
Which ONE of the following six-factor formula factors is the most affected by a negative temperature coefficient?
a.
Fast fission factor b.
Thermal utilization factor c.
Fast non-leakage probability d.
Thermal non-leakage probability QUESTION A.10
[1.00 point]
Which ONE of the following is the definition of the term Shutdown Margin?
a.
the departure from k-effective = 1.00 b.
the time required for the blades to fully insert.
c.
the amount of reactivity by which the reactor is subcritical.
d.
the amount of reactivity inserted by all the rods except the most reactive blade and the regulating rod.
QUESTION A.11
[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 amount of reactivity that a given unit of rod motion would insert at that position in the core.
d.
The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.12
[1.00 point]
At the beginning of a reactor startup, k-effective is 0.90 with a count rate of 30 count per second (cps). Power is increasing to a new, steady value of 60 cps. Which ONE of the following is the new k-effective?
a.
0.95 b.
0.92 c.
0.86 d.
0.77 QUESTION A.13
[1.00 point]
Which ONE of the following changes in reactor power would take the LONGEST time?
Assume the reactor is on a constant period.
a.
400 W to 500 W b.
100 kW to 400 kW c.
3.5 MW to 4.5 MW QUESTION A.14
[1.00 point]
Which ONE of the following is the effect of delayed neutrons on the reactor power following a scram from full power?
a.
decreases the mean neutron lifetime.
b.
adds negative reactivity creating a greater shutdown margin.
c.
limits the final rate at which power decreases to a negative 80 second period.
d.
add positive reactivity due to the fuel temperature decrease following the scram.
QUESTION A.15
[1.00 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
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16
[1.00 point]
During a reactor startup, you increase reactor power from 100 kW to 195 kW in a minute.
Which ONE of the following is the reactor period?
a.
45 seconds b.
58 seconds c.
90 seconds d.
110 seconds QUESTION A.17
[1.00 point]
If beta for U-235 is 0.0065 and beta effective is approximately 0.007, then the period is _______
when beta effective is used instead of beta in the reactor period equation =
a.
decay constant () increase b.
stable period c.
shorter period d.
longer period QUESTION A.18
[1.00 point]
The following graph for U-235 depicts which ONE of the following?
a.
fission product yield distribution b.
radial flux distribution in the core c.
axial flux distribution in the core d.
neutron energy distribution in the moderator
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19
[1.00 point]
Which ONE of the following is the definition of reactivity?
a.
fractional departure from criticality b.
rate of change of the reactor power in neutron per second 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.20
[1.00 point]
The graph below depicts the different regions of operation for a gas filled detector. Which ONE of the following labels is the Geiger-Mueller region?
a.
Section B b.
Section C c.
Section D d.
Section E
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01
[1.00 point]
Which ONE of the following is the 10 CFR 20 definition of Total Effective Dose Equivalent (TEDE)?
Total Effective Dose Equivalent (TEDE) is __________.
a.
The sum of the external deep dose and the organ dose.
b.
The dose that your whole body receives from sources outside the body.
c.
The dose to a specific organ or tissue resulting from an intake of radioactive material.
d.
The sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).
QUESTION B.02
[1.00 point]
In accordance with the MURR Emergency Plan, the Emergency Director shall have all the direct responsibilities EXCEPT:
a.
Responsibility to identify and classify the emergency.
b.
Responsibility for terminating an emergency and initiating recovery action.
c.
Responsibility for evaluating evacuation activities.
d.
Responsibility for authorizing volunteer emergency workers to incur radiation exposure in excess of normal occupational limits.
QUESTION B.03
[1.00 point]
When the reactor is operated, the reactor shall have a shutdown margin of at least 0.02 k/k. Which ONE of the following is NOT an associated required condition?
a.
The reactor is in the reference core condition.
b.
The regulating blade and most reactive shim blade in their fully withdrawn positions.
c.
The rate of fission product decay.
d.
Irradiation facilities and experiments in place and the total worth of all experiments in their most reactive state.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04
[1.00 point]
If a radiation source reads 50 R/hr at 1ft, what is the dose rate at 10 ft?
a.
10 mR/hr.
b.
100 mR/hr.
c.
500 mR/hr.
d.
10 R/hr.
QUESTION B.05
[1.00 point]
In accordance with Operations Procedure 105, which ONE of the following ensures all personal requalification requirements are completed as required by this procedure?
a.
Individual licensed operator b.
Assistant Reactor Manager - Training c.
Assistant Reactor Manager - Operations d.
Reactor Manager QUESTION B.06
[1.00 point]
You are a licensed operator at MURR and conducted 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of licensed activities last quarter. Which ONE of the following regulations does this violate and how many hours are required per quarter?
a.
10 CFR 20.1201, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> b.
10 CFR 50.59, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> c.
10 CFR 55.53, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> d.
10 CFR 37.23, 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> complies
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07
[1.00 point]
Which ONE of the following is the best definition of the Emergency Planning Zone (EPZ)?
a.
The EPZ area bounded by a 150-meter radius from the exhaust stack and lies completely within site boundary.
b.
The EPZ may be used as a central point for the receipt and evaluation of radiological data, and it is where emergency control directions can be given.
c.
The EPZ is the area limited to the licensee for the purpose of protecting individuals against undue risk from exposure to radiation and radioactive materials.
d.
The EPZ is the area where the Emergency Coordinator has direct authority over all activities; it has prearranged evacuation procedures known to personnel frequenting the area.
QUESTION B.08
[1.00 point]
In accordance with MURR Administrative Procedure, Periodic Document Review, AP-DC-105, which ONE of the following MURR documents is NOT a controlled document that must be reviewed on an annual basis?
a.
Personnel Access and Accountability Roster b.
Operator Requalification Program c.
Physical Security Plan QUESTION B.09
[1.00 point]
A reactor operator (RO) works in a high radiation area for eight hours a day. The dose rate in the area is 50 mrem/hr. Which ONE of the following is the MAXIMUM number of days in which the RO may perform his duties WITHOUT exceeding their 10 CFR 20 limits?
a.
10 days b.
11 days c.
12 days d.
13 days
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10
[1.00 point, 0.25 each]
Identify each MURR Technical Specification definition listed below as: 1. Safety Limit (SL),
- 2. Limiting Safety System Setting (LSSS), 3. Limiting Conditions of Operation (LCO), or 4.
Operable (Op). Answers may be used once, more than once, or not at all.
a.
component or system is capable of performing its intended function.
b.
established constraints on equipment and operational characteristics that shall be adhered to during operation of the facility.
c.
limits placed upon important process variables which are found to be necessary to reasonably protect the integrity of the principal physical barriers which guard against the uncontrolled release of radioactivity.
d.
settings for automatic protection devices related to those variables having significant safety functions.
QUESTION B.11
[1.00 point]
Which ONE of the following is the 10 CFR 20 definition of Dose Equivalent?
a.
The sum of the external deep dose and the organ dose.
b.
The dose that your whole body receives from sources outside the body.
c.
product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest.
d.
that portion of the exposure received from the radiation sources outside the body.
QUESTION B.12
[1.00 point]
In accordance with MURR Emergency Procedures, EP-RO-001, which ONE of the following is NOT classified as On-Site?
a.
South of Stadium Boulevard b.
North of the MU Recreation Trail c.
East of Route K (Providence Road) d.
East of the MKT Nature and Fitness Trail
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13
[1.00 point]
A 2 Curie radioactive point source results in an emission of a 100 keV gamma, 80% of the time. What is the dose rate at one foot?
a.
196 mRem/hr.
b.
960 mRem/hr.
c.
1.96 Rem/hr.
d.
396 Rem/hr.
QUESTION B.14
[1.00 point]
In accordance with MURR Operator Requalification Program, which ONE of the following defines critical steps?
a.
the most time-consuming parts of the process.
b.
the steps that if performed incorrectly or not at all would prevent the system from operating safely.
c.
all the steps that require a high level of expertise and advanced skill.
d.
the steps that are necessary to complete a task as intended to sign off.
QUESTION B.15
[1.00 point]
In accordance with 10 CFR 20, which ONE of the following defines Whole Body?
a.
Head to toe coverage.
b.
All body parts that are exposed to the radiation hazard.
c.
Shoulders to the waist.
d.
External exposure, head, trunk, arms above the elbow, or legs above the knee.
QUESTION B.16
[1.00 point]
In accordance with MURR Operations Procedure Manual, AP-RO-110, which ONE of the following is the individual responsible with the specific written authority to approve use of corrosive chemicals for use in reactor systems?
a.
Reactor Operator b.
Senior Reactor Operator c.
Reactor Manager d.
Reactor Director
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B. 17
[1.00 point]
In accordance with MURR Facility Procedures Manual, AP-RR-001, which ONE of the following is responsible for developing and implementing corrective actions relative to Personnel Safety Issues?
a.
Reactor Operator b.
Senior Reactor Operator c.
Reactor Manager d.
Environmental Health and Safety Manager QUESTION B.18
[1.00 point]
In accordance with MURR Technical Specifications, for Mode III operation, the high power scram will occur at ________ and there is a margin of _______ between the limiting safety system setting (LSSS) and the operating limit of ________.
a.
62.5 kW, 87.5 kW, 150 kW b.
72.5 kW, 89.5 kW, 175 kW c.
90 kW, 100 kW, 2.0 MW d.
25.5 kW, 115 kW, 2.5 MW QUESTION B.19
[1.00 point]
In accordance with MURR Reactor Emergency Procedures Manual, REP-RO-110, if any Limiting Safety System Setting (LSSS) malfunctions and an analysis determines it did not exceed limitations, which ONE of the following gives permission for resumed reactor operation?
a.
Reactor Operator b.
Senior Reactor Operator c.
Reactor Manager d.
Reactor Director
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.20
[1.00 point]
In accordance with MURR Emergency Procedures Manual, REP-17, which ONE of the following is NOT an immediate action in response to a loss of pool water during reactor operation?
a.
Manually scram the reactor.
b.
Close valve 547 and ensure the valve indicates shut.
c.
Verify all rods are bottomed.
d.
Place P513B switch to ON.
(***** END OF CATEGORY B *****)
Category C: Facility and Radiation Monitoring Systems QUESTION C.01
[1.00 point]
Which ONE of the following devices is BEST suited for measuring cumulative occupational dose over a several month period?
a.
Electronic Personal Dosimeter (EPD) b.
Optically Stimulated Luminescent Dosimeter (OSL) c.
Personal Ion Chamber (PIC) d.
Dose Area Product Meter (DAP)
QUESTION C.02
[1.00 point]
In accordance with MURR Calibration-Radiation Survey Instruments, IC-HP-300, which ONE of the following is determined in the measured activity(cpm)/calibrated activity (cpm)?
a.
final activity of the source b.
dose rate of the source c.
efficiency of the source d.
half-life of the source QUESTION C.03
[1.00 point]
In accordance with MURR Sealed Calibration Source-Leak Check, SV-HP-105, which ONE of the following requires dosimetry sensitive to neutron radiation?
a.
Am-241 leakage test b.
Cs-137 source test c.
B-10 strength test d.
Cf-252 source test QUESTION C.04
[1.00 point]
In accordance with MURR Property Release, SV-HP-119, which ONE of the is the process of making a radioisotope by bombarding a stable element with neutrons or protons?
a.
Activation b.
Contamination c.
Decontamination d.
Spontaneous Decay
Category C: Facility and Radiation Monitoring Systems QUESTION C.05
[1.00 point]
In accordance with MURR Property Release, SV-HP-119, which ONE of the following would indicate property is contaminated?
a.
A swipe reading 150 cpm as read by a High Purity Germanium detector.
b.
An indication of 20 dpm on a pancake probe.
c.
A Geiger-Mueller frisker indication of 200 cpm.
d.
A swipe reading 100 dpm as read by a Gas-Flow Proportional counter.
QUESTION C.06
[1.00 point]
In accordance with MURR Technical Specifications, which ONE of the following is the primary air effluent by which the dispersion calculations are based?
a.
Ar-41 c.
Cs-137 d.
U-233 QUESTION C.07
[1.00 point]
In accordance with MURR Technical Specifications, which ONE of following is the radiation monitor that may be placed out of service for up to two hours for calibration and maintenance?
a.
Reactor Bridge Monitor b.
Off-Gas Radiation Monitor c.
Reactor Containment Building Exhaust Plenum Radiation Monitor d.
None of the above, must secure and shutdown the reactor QUESTION C.08
[1.00 point]
Which ONE of the following receives DC input from parallel sources and converts the DC to a step-like AC?
a.
Inverter b.
Charger c.
Battery Bank d.
Static Switch
Category C: Facility and Radiation Monitoring Systems QUESTION C.09
[1.00 point]
Which ONE of the following is NOT directly powered by the Emergency Power Panel?
a.
Airlock Doors b.
Door 504 & 505 c.
Emergency Air Compressor d.
Facility Exhaust Fans QUESTION C.10
[1.00 point]
Which ONE of the following is the system that consists of three sections: water treatment section, reactor storage tanks, and facility storage tanks?
a.
Steam and Condensate System b.
Liquid Waste Retention System c.
Demineralized Water Supply System d.
Facility Drainage and Sump System QUESTION C.11
[1.00 point]
In accordance with MURR Technical Specifications, which ONE of the following is the frequency and acceptable limit for pH?
a.
pool coolant system 4.5 average over a month b.
primary coolant system pH 6.5 averaged over one quarter c.
annual average pH of 7.5 d.
secondary coolant system pH 7.0 over a week QUESTION C.12
[1.00 point]
In accordance with MURR Technical Specifications, which ONE of the following assures protection of the fuel elements from a continuous blade withdrawal accident?
a.
power level interlock b.
reactor period scram c.
anti-siphon high level rod run-in d.
regulating blade rod run-ins
Category C: Facility and Radiation Monitoring Systems QUESTION C.13
[1.00 point]
In accordance with MURR Technical Specifications, which ONE of the following is NOT true?
a.
above 100 kW, the reactor shall be operated with the maximum distance between the blades not exceeding one inch.
b.
maximum rate of reactivity insertion for the regulating blade shall not exceed 1.5 x 10-4 k/k/seconds.
c.
shim blades shall be capable of insertion to the 20% withdrawn position in less than 0.7 seconds.
d.
maximum rate of reactivity insertion for the four shim blades shall not exceed 1.5 x 10-4 k/k/seconds.
QUESTION C.14
[1.00 point]
In accordance with MURR Technical Specifications, which ONE of the following is correct?
a.
Mode II reactor period requires three indications and the trip set point is 15 seconds.
b.
Mode III vent tank low level requires two indications with a trip set point of 2 feet below centerline.
c.
Mode I high power level requires three indications with a 115% trip set point at full power.
d.
Mode II pool low water level requires one indication with a trip set point at 28 feet.
QUESTION C.15
[1.00 point]
In accordance with MURR Visitor Dosimetry-Reception Desk, AP-HP-123, which ONE of the following is NOT correct concerning issuance of Electronic Personnel Dosimeters (EPD)?
a.
If the visitor is part of a group, issue an EPD to one individual for every five group members.
b.
If a visitor enters an area with a radiation dose of greater than 2 mRem/hr, they must be issued an EPD.
c.
If the visitor may receive a total dose greater than 10 mRem for the entire visit they must be issued an EPD.
d.
If the visitor needs to enter a Radiation Area, then each visitor must be issued their own EPD.
Category C: Facility and Radiation Monitoring Systems QUESTION C.16
[1.00 point]
Which ONE of the following is the location where domestic water enters the facility?
a.
laboratory basement b.
area outside mechanical equipment room 114 c.
southwest corner of the cooling tower basement d.
Missouri University Research Reactor (MURR) industrial building QUESTION C.17
[1.00 point]
Which ONE of the following best describes the signal path for the power range monitor #5 instrument loop?
a.
Fission Chamber #2 IsolatorPre-AmplifierAnnunciator b.
Fission Chamber #2IsolatorPower Down ScaleAnnunciator c.
Fission Chamber #2Pre-AmplifierIsolatorRemote Chart Recorder
- d. Fission Chamber #2Pre-AmplifierLocal Level DisplayAuto Control Interlock QUESTION C.18
[1.00 point]
Which ONE of the following is NOT a primary coolant system indication located on the control room instrument panel?
a.
HX503A Out Temperature b.
Reactor Core Inlet Temperature c.
Off/On Indication for P508A and P508B d.
Off/On Indication for P501A and P501B
Category C: Facility and Radiation Monitoring Systems QUESTION C.19
[1.00 point]
If pressurizer liquid level decreases below the normal operating level, which ONE of the following actions does NOT occur?
- a. At approximately 7 inches (17.78 cm) below centerline, LC 936 signals water addition valve V527B to open and start coolant charging pump 533, adding water to the pressurizer
- b. At approximately 13 inches (33.0 cm) below center line, the surge line isolation valve V527C closes to prevent the introduction of nitrogen gas into the primary coolant system c.
At approximately 13 inches (33.0 cm) below center line, LC935 initiates a reactor scram by opening a contact (K28-2) in the process input string to E3B of the Reactor Safety System NCLUs.
- d. At approximately 11 inches (27.94 cm below center line LC 937 initiates a pressurizer water to level annunciator alarm and signals valve V527A to close.
QUESTION C.20
[1.00 point]
Which ONE of the following best describes the flow path of the pool coolant demineralizer loop?
a.
Reactor PoolPool Demin PumpPool Inlet FilterDI TankPool Outlet Filters b.
Pool Inlet FilterDI TankPool Outlet FiltersPool Demin PumpReactor Pool c.
Reactor PoolPool Outlet FiltersPool Demin PumpPool Inlet FilterDI Tank d.
DI tankDemin PumpPool Inlet FilterReactor PoolPool Outlet Filter
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer:
d
Reference:
CR=S/(1-k)250/(1-0.5) = 500 N/sec A.02 Answer:
a
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 5.4 A.03 Answer:
b
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2 A.04 Answer:
c
Reference:
P = P0 et/T --> T= t/Ln(P/ P0 )
T= 45/Ln(100/50 ); T = 64.9 seconds or 65 seconds A.05 Answer:
a
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Volume 1, Section 3.2 A.06 Answer:
d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations A.07 Answer:
d
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 4, page 15 A.08 Answer:
b
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Volume 3, Section 4.6 Shutdown reactor, T = -80 seconds; Time = 120 seconds P = Po et/T -> 3 x 106 e -120/80 = 6.69 x 105 A.09 Answer:
b
Reference:
Glasstone, S. and Sesonske, A., Nuclear Reactor Engineering, 1991, page 264 A.10 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, Volume 3, Section 6.2.3 A.11 Answer:
c
Reference:
Burn, Introduction to Nuclear Reactor Operations, Table 3.5, page 3-22
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.12 Answer:
a
Reference:
(CR2/CR1) = (1-Keff0)/(1-Keff1) = (60/30) = (0.90)(1-Keff1); Keff1 = 0.95 A.13 Answer:
b
Reference:
P = P0 et/T, P/ P0 = et/T, Ln (P/ P0) = t/T. Ln(400/100) = t/T, Ln (4) = t/T = 1.386, answer (b) power manipulations would take the longest time to complete A.14 Answer:
c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, Volume 2, Section 4.10.12, pages 4-32 & 4-33 A.15 Answer:
c
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, NP-03, page 9 A.16 Answer:
c
Reference:
P = P0
= t/ln(P/P0) = 60/ln (195/100) = 60/ln(1.95) = 89.84 or 90 sec.
A.17 Answer:
d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, example 3.4.3, pages 3-32
& 3-33 A.18 Answer:
a
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 1, page 57 A.19 Answer:
a
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 1.3.1, page 1-5
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.20 Answer:
- d. E. NOT D.
Reference:
NRC Standard Question
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer:
d
Reference:
10 CFR 20.1003, Definitions B.02 Answer:
c
Reference:
MURR Emergency Plan 2.2 and 2.3 B.03 Answer:
c
Reference:
MURR Technical Specifications 3.1.b B.04 Answer:
c
Reference:
50 R/hr at (1 ft)2 = X R/hr. at (10ft)2 50 x 12 / 102 = 500 mR/hr.
B.05 Answer:
a
Reference:
MURR Operations Procedure 105, 4.0 and MURR Operator Requalification Program 2.1 B.06 Answer:
c
Reference:
10 CFR 55.53 B.07 Answer:
a
Reference:
MURR Emergency Procedure, EP-RO-001, 1.11 B.08 Answer:
a
Reference:
MURR Administrative Procedure, Periodic Document Review, AP-DC-105, 5.0 B.09 Answer:
c
Reference:
10 CFR 20.1201(a)(1); (5000 mR x 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> x 1 day) / (50 mR x 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) = 12.5 days; If you round up it exceeds the limit B.10 Answer:
Reference:
MURR Technical Specifications 1, Definitions and 3, Limiting Conditions of Operation B.11 Answer:
c
Reference:
10 CFR 20.1003 B.12 Answer:
c
Reference:
MURR Emergency Procedures, EP-RO-001, 1.21
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.13 Answer:
b
Reference:
6 Cen = R/hr @ 1 ft; 6 x 2 x 0.8 x 0.1 = 0.96 R/hr @ 1 ft. or 960 mRem B.14 Answer:
b
Reference:
MURR Operator Requalification Program, page A-5 B.15 Answer:
d
Reference:
10 CFR 20.1003 B.16 Answer:
c
Reference:
MURR Operations Procedure Manual, AP-RO-110, 5.5 B.17 Answer:
d
Reference:
MURR Facility Procedures Manual, AP-RR-001, 4.11, page 11 B.18 Answer:
a
Reference:
MURR Technical Specifications 2.2 B.19 Answer:
c
Reference:
MURR Emergency Procedures Manual, REP-RO-100, Introduction B.20 Answer:
d
Reference:
MURR Emergency Procedures Manual, REP-17 Immediate Actions
(***** END OF CATEGORY B *****)
Category C: Facility and Radiation Monitoring Systems C.01 Answer:
b
Reference:
NRC Standard Question C.02 Answer:
c
Reference:
MURR Calibration - Radiation Survey Instruments, IC-HP-300 6.3.3 C.03 Answer:
d
Reference:
MURR Sealed Calibration Source-Leak Check, SV-HP-105 5.0 C.04 Answer:
a
Reference:
MURR Property Release, SV-HP-119, 3.0 C.05 Answer:
c
Reference:
MURR Property Release, SV-HP-119, 4.3 C.06 Answer:
b
Reference:
MURR Technical Specifications 3.7 C.07 Answer:
b
Reference:
MURR Technical Specifications 3.7 C.08 Answer:
a
Reference:
MURR Training Manual Uninterruptible Power Supply, II C.09 Answer:
d
Reference:
MURR Training Manual Emergency Electrical Distribution, I.B C.10 Answer:
c
Reference:
MURR Training Manual Demineralized Water Supply System, II C.11 Answer:
b
Reference:
MURR Technical Specifications 3.3 C.12 Answer:
b
Reference:
MURR Technical Specifications 3.2 C.13 Answer:
d
Reference:
MURR Technical Specifications 3.2
Category C: Facility and Radiation Monitoring Systems C.14 Answer:
c
Reference:
MURR Technical Specifications 3.2 C.15 Answer:
b
Reference:
MURR Visitor Dosimetry-Reception Desk, AP-HP-123, 4.0 C.16 Answer:
c
Reference:
MURR Operations Training Manual, Page 1-1A C.17 Answer:
c
Reference:
MURR Operations Training Manual, Page 8-9A C.18 Answer:
c
Reference:
MURR Operations Training Manual, Page 3-4A C.19 Answer:
d
Reference:
MURR SAR 7.6.5, Page 307 C.20 Answer:
a
Reference:
MURR Operations Training Manual, Page 1-5E
(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **********)