ML23198A012
| ML23198A012 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 12/12/2023 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Joel Jenkins Texas A&M Univ |
| References | |
| 50-128/23-03 50-128/OL-23 | |
| Download: ML23198A012 (34) | |
Text
December 12, 2023 Jere Jenkins, Director Nuclear Engineering and Science Center Texas Engineering Experiment Station 1095 Nuclear Science Road, MS 3575 College Station, TX 77843-3575
SUBJECT:
EXAMINATION REPORT NO. 50-128/OL-23-03, TEXAS A&M UNIVERSITY
Dear Jere Jenkins:
During the week of September 25, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Texas A&M University Engineering Experiment Station reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2.
Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.
In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records 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 John T. Nguyen at (301) 415-4007 or via email at John.Nguyen@nrc.gov.
Sincerely, Travis L. Tate, 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-23-03
- 2. Written examination cc: w/o enclosures to GovDelivery Subscribers Signed by Tate, Travis on 12/12/23
ML23198A012 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME JNguyen NJones TTate DATE 11/14/2023 12/12/2023 12/12/2023 U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-128/OL-23-03 FACILITY DOCKET NO.:
50-128 FACILITY LICENSE NO.:
R-83 FACILITY:
Texas A&M University EXAMINATION DATES:
September 25-29, 2023 SUBMITTED BY: John Nguyen 11/08/2023 John T. Nguyen, Chief Examiner Date
SUMMARY
During the week of September 25, 2023, the NRC administered operator licensing examinations to three Reactor Operator-Instant (ROI), one Reactor Operator - Retake (ROR) for Part A of the written examination, and two Senior Reactor Operators - Instant (SROI) candidates. One ROI failed the written examination and the operation test. All other candidates passed all applicable portions of the examinations and tests.
REPORT DETAILS 1.
Chief Examiner: John T. Nguyen, Chief Examiner, NRC 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/1 2/0 5/1 Operating Tests 2/1 2/0 4/1 Overall 3/1 2/0 5/1 3.
Exit Meeting:
Jere Jenkins, TEES Director John T. Nguyen, Chief Examiner, NRC Facility comments were accepted prior to the administration of the written examination.
At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examinations. The examiner discussed the candidates weaknesses observed during the operating tests, especially discussed significant deficiencies in the ROI candidate who failed the written examination and the operation test. The facility indicated that it would implement an adequate corrective action to improve the training and screening processes to ensure the candidates sufficient knowledge before sitting for the NRC examination.
Texas Engineering Experiment Station Operator Licensing Examination Week of September 25, 2023
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
University of Texas A&M REACTOR TYPE:
TRIGA DATE ADMINISTERED:
09/27/2023 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 FINAL GRADE TOTALS 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.
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 or X your choice)
If you change your answer, write your selection in the blank.
A01 a b c d ___
A02 a b c d ___
A03 a b c d ___
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 ___ (0.25 each)
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 or X your choice)
If you change your Answer, write your selection in the blank.
B01 a ___ b ___ c ___ d ___ (0.25 each)
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 ___ (0.25 each)
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 ___ (0.25 each)
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 or X your choice)
If you change your Answer, write your selection in the blank.
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 ___ (0.25 each)
C11 a b c d ___
C12 a b c d ___
C13 a b c d ___
C14 a ___ b ___ c ___ d ___ (0.25 each)
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 ___ (0.25 each)
C20 a ___ b ___ c ___ d ___ (0.25 each)
(***** 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
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
eff 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
[1.0 point]
If 0.156 % k/k of positive reactivity is suddenly introduced into a stable power of 100 W, what will be the steady period that is obtained? Assume the effective prompt neutron lifetime is 10-4 seconds, the effective delayed neutron decay constant is 0.1 s-1, and the effective delayed neutron fraction is 0.0078.
a.
10 seconds b.
29 seconds c.
40 seconds d.
80 seconds QUESTION A.02
[1.0 point]
Which ONE of the following isotopes has the HIGHEST thermal neutron cross section?
a.
Cd-112 b.
Sm-149 c.
Xe-135 d.
U-238 QUESTION A.03
[1.0 point]
Which ONE of the following is the stable reactor period which will result in a power rise from 1%
to 100% power in 1 minute?
a.
0.2 seconds b.
2 seconds c.
13 seconds d.
20 seconds
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04
[1.0 point]
Which type of neutron interaction (light nuclei) is most important in moderating fast neutrons to thermal neutrons?
a.
Fission b.
Elastic scattering c.
Inelastic scattering d.
Neutron capture QUESTION A.05
[1.0 point]
What is the meaning of any point on a differential rod worth curve?
a.
The cumulative area under the differential curve starting from the bottom of the core.
b.
The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn.
c.
The amount of reactivity that one unit (e.g. one inch, one percent) of rod motion would insert at that position in the core.
d.
The amount of reactivity that one unit (e.g. one inch, one percent) of rod motion would fully insert to the bottom of the core from that position.
QUESTION A.06
[1.0 point]
The probability of neutron nucleus interaction per centimeter of neutron travel is defined as:
- a.
Macroscopic Cross Section b.
Mean free path c.
Neutron flux d.
Barn
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.07
[1.0 point]
What effect does Doppler Broadening for U-238 have on neutrons in a critical core?
a.
More fission.
b.
More absorption.
c.
Increasing the Reproduction factor.
d.
Increasing the resonance escape probability.
QUESTION A.08
[1.0 point]
Which ONE of the following is true regarding the term, subcritical multiplication? As the reactor approaches criticality, the parameter ___________.
a.
keff approaches zero b.
1/M approaches zero c.
M approaches one d.
approaches infinity QUESTION A.09
[1.0 point]
Which ONE of the following statements is true regarding to Xe-135 poison in the TAMU reactor?
a.
There are two methods forming Xe-135 poison: by decay of I-135 and decay of Cs-135.
b.
As Xe-135 is formed in the reactor, the thermal utilization factor will increase.
c.
Xe-135 can be formed directly as a fission product.
d.
Xe-135 is never reach equilibrium during reactor operation.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.10
[1.0 point]
Which ONE of the following changes will require the control rod INSERTION to maintain constant power level? Assume a reactor is in steady-state mode.
a.
Burn-up Xenon in the core.
b.
Insertion of an experiment containing cadmium.
c.
Pool water temperature increase.
d.
Buildup of Samarium in the core.
QUESTION A.11
[1.0 point]
A reactor is subcritical with a shutdown margin of 5.0 % K/K. The addition reactivity worth is added and the count rate increases from 400 count per seconds to 800 count per seconds (cps).
The new Keff of the reactor is ________.
a.
0.535 b.
0.905 c.
0.975 d.
1.025 QUESTION A.12
[1.0 point]
A reactor is in an automatic mode of 500 kW. What will the safety rod do if its boron graphite is replaced with void (air)?
a.
Drive out to compensate a positive reactivity added.
b.
Drive out to compensate a negative reactivity added.
c.
Drive in to compensate a positive reactivity added.
d.
Drive in to compensate a negative reactivity added.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13
[1.0 point]
Delayed neutrons are born at ________ energies than prompt neutrons which leads to the delayed neutron fraction being _______ than the effective delayed neutron fraction.
a.
lower; lower b.
lower; higher c.
higher; lower d.
higher; higher QUESTION A.14
[1.0 point]
Which ONE of the following factors in the six factor formula is the MOST affected by the MODERATOR?
a.
Fast fission factor b.
Reproduction factor c.
Thermal utilization factor d.
Resonance escape probability QUESTION A.15
[1.0 point]
A reactor contains a neutron source that produces 10,000 neutrons/second with a keff of 0.80.
What is the stable total neutron production rate in the reactor?
a.
20,000 neutrons/sec b.
50,000 neutrons/sec c.
80,000 neutrons/sec d.
200,000 neutrons/sec
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16
[1.0 point, 0.25 each]
Match the following Neutron Interactions in Column A with the appropriate definition in Column B (each used only once)
Column A Column B
- a.
Fission
- 1. Neutron enters nucleus, forms a compound nucleus, then decays by gamma emission.
- b.
Capturing
- 2. Particle enters nucleus, forms a compound nucleus and is excited enough to eject a new particle with incident neutron remaining in nucleus.
- c.
Scattering
- 3. Nucleus absorbs neutron and splits into two similarly sized parts.
- d.
Particle ejection
- 4. Nucleus is struck by a neutron and emits a single neutron.
QUESTION A.17
[1.0 point]
Reactor is critical at 100 watts. A reactor operator makes a mistake by inserting a sample worth of $1 into the reactor core. Which ONE of the following best describes the reactor kinetic?
- a.
Keff = 1 and = 0
- b.
Keff > 1 and = effective c.
Keff > 1 and = 1 k/k d.
Keff > 1 and 0 < < effective QUESTION A.18
[1.0 point]
Reactor A has a Keff of 0.1 while a reactor B has a Keff of 0.8. If Keff is increased by 0.05 for each reactor. The amount of reactivity added in reactor A is ______ in reactor B for the same amount of increment.
- a.
less than
- b.
same
- c.
thirty-six times
- d.
forty-five times
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19
[1.0 point]
Which ONE of the following atoms will cause a neutron to lose the most energy in an elastic collision?
a.
U-238 b.
Ar-40 c.
O-16 d.
H-1 QUESTION A.20
[1.0 point]
Which ONE of the following is the major source of heat generated after an operating reactor has been shut down and cooled down for several days?
- a.
N-16 production.
- b.
Fission fragment decay.
- c.
Delayed neutron reactions.
- d.
Corrosion product activation.
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01
[1.0 point, 0.25 each]
Match the radiation reading from Column A with its corresponding radiation area classification (per 10 CFR 20) listed in Column B. Answer in Column B can be used more than once, or not at all. Assume the radiation source listed on column A can be a point source.
Column A Column B
- a.
2 mrem/hr at 1 m
- 1. Public Area b.
20 mrem/hr at 1 m
- 2. Radiation Area c.
50 mrem/hr at 1 m
- 3. High Radiation Area d.
4.50 grays/hr at 1 m
- 4. Very High Radiation Area QUESTION B.02
[1.0 point]
Which ONE of the following radionuclides causes a radiation internal hazard if intaking internally?
a.
N16 c.
Ar41 d.
O16 QUESTION B.03
[1.0 point]
Which ONE of the following conditions is considered a damaged fuel element?
a.
Its length exceeds its original length by 0.120 inches.
b.
Visual inspection reveals a brownish color in the middle of fuel element.
- c.
The transverse bend exceeds 0.120 inches over the length of the cladding.
d.
Visual inspection reveals a corrosion in the middle of fuel element.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04
[1.0 point]
Per NSCR Technical Specifications, which ONE of the following is an acceptable value (conductivity/resistivity) for the bulk pool water?
a.
10 x 10-6 mhos/cm b.
5 x 10-6 mhos/cm c.
10 x 10-6 ohms/cm d.
5 x 10-6 ohms/cm QUESTION B.05
[1.0 point]
All applicants for an RO or SRO license must take the medical examination in accordance with 10 CFR ________.
a.
Part 19 b.
Part 20 c.
Part 50 d.
Part 55 QUESTION B.06
[1.0 point]
The Annual Limit on Intake (ALI) is defined as:
a.
The concentration of a given radionuclide in air which, if breathed by an adult worker for a year, would result in a committed effective dose equivalent of 5 rems.
b.
The dose equivalent to organs or tissues that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.
c.
The concentration of a given radionuclide in air which, if breathed by an adult worker for a year, would result in a committed effective dose equivalent of 15 rems.
d.
The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year that would result in a committed effective dose equivalent of 5 rem whole body or 50 rems to any individual organ or tissue.
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07
[1.0 point, 0.25 each]
Match the appropriate radiation unit in Column A with its definition in Column B.
Column A Column B
- a.
Curie
- 1. Equal to absorbed dose of 100 ergs/gram
- b.
Roentgen
- 2. Amount of radioactive material decaying at a rate of 3.7x1010
- c.
RAD
- 3. Amount of x-ray or gamma ray leading to the absorption of 88 ergs/gram in air
- d.
Dose Equivalent
- 4. Equal to absorbed dose in RAD times quality factor QUESTION B.08
[1.0 point]
A room contains a source which, when exposed, results in a general area dose rate of 500 millirem per hour. This source is scheduled to be exposed continuously for 20 days. Which ONE of the following statements correctly describes an acceptable method for controlling radiation exposure from the source within this room?
a.
Monitor the current dose rate in the reactor control room.
b.
Post the area with Caution - Contamination Area.
c.
Control is not required because the presence of radioactive source is less than 30 days.
d.
Equip the room with an electronic surveillance that can prevent unauthorized entry.
QUESTION B.09
[1.0 point]
A 40-mm thick sheet of lead placed at a certain location in a beam port reduced the gamma radiation level from 600 mR/hr to 150 mR/hr. How many total thicknesses of lead would be needed to reduce the gamma radiation level from 600 mR/hr to 75 mR/hr?
a.
20 mm b.
40 mm c.
60 mm d.
80 mm
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10
[1.0 point]
Per NSCR Emergency Plan, the individual who is responsible for the termination of an emergency is the ____________.
a.
NSCR Police Chief b.
Public Relations Coordinator c.
NSCR Radiation Protection Officer d.
NSCR Emergency Director QUESTION B.11
[1.0 point]
After a long period of reactor operation, the staffs perform a normal shutdown checklist and find that all the control rods are fully inserted except a stuck control rod. Which ONE of the following is the MINIMUM staffing requirement for this condition?
a.
All staffs may go home after the shutdown checklist is completed because the reactor meets a shutdown definition.
b.
Require only one licensed reactor operator (RO) present in the control room.
c.
Require one SRO at the facility complex and one RO in the control room.
d.
Require one SRO in the control room, and one RO and one trainee at the facility complex.
QUESTION B.12
[1.0 point, 0.25 each]
Identify the PRIMARY source (irradiation of air, irradiation of water, irradiate of reactor structure, or fission product) of EACH of the following radioisotopes.
- a.
Al-28
- b.
Ar-41
- c.
- d.
Xe-131
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13
[1.0 point]
Which ONE of the following would violate the Limiting Safety System Setting (LSSS) of the NSCR Technical Specifications?
- a.
The maximum reactivity in excess of reference core condition exceeds 6.5% k/k.
- b.
The pool water temperature exceeds 60 °C.
- c.
The fuel temperature cladding exceeds 975°F.
- d.
The reactor power exceeds 1.2 MW when an experiment fails.
QUESTION B.14
[1.0 point]
Per NSCR Emergency Classification, the emergency classification in which significant releases of radioactive materials as a result of experiment failures is defined as:
a.
Alert b.
Unusual Event c.
Abnormal Condition but Not Related to Reactor Safety.
d.
Non-Reactor, Safety-Related Event QUESTION B.15
[1.0 point]
A semi-annual test of the nuclear instrument was performed. Which ONE of the following is the latest the test that must be performed again without violation of the Technical Specifications?
a.
6 months b.
7 months c.
8 months d.
9.5 months
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16
[1.0 point]
Which ONE of the following surveillances is a channel check?
a.
Disconnecting the HV neutron flux channel to verify a reactor scram.
b.
Comparing the readings of the safety channels during reactor operation.
c.
Exposing a check source to the reactor bay radiation area monitor to verify its operation.
d.
Adjusting a power level based on the thermal power calibration.
QUESTION B.17
[1.0 point]
In the event of injury with contamination, which ONE of the following hospitals is the individual transported to?
- a.
St. Joseph Health College Station
- b.
Baylor Scott & White Hospital c.
Bryan Medical Center d.
Nova Medical Center QUESTION B.18
[1.0 point]
A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 350 mrem/hour with the window opened (assume no alpha) and 100 mrem/hour with the window closed. A ratio between a gamma dose/beta dose rate is:
a.
0.40 (100/250 mrem/hr) b.
1.0 (250/250 mrem/hr) c.
0.28 (100/350 mrem/hr) d.
0.71 (250/350 mrem/hr)
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19
[1.0 point]
A five-curie source emits a 100 keV gamma 75% of the time. The source will be placed in the reactor storage room. How far from the source should a radiation area sign be posted?
a.
5.2 feet b.
10.2 feet c.
21.2 feet d.
31.2 feet QUESTION B.20
[1.0 point]
In accordance with NESC SOP-II-C, which ONE of the following is correct regarding reactor experiment?
a.
The reactivity worth of any experiment being moved manually shall be less than $0.50.
b.
Any movable experiment with reactivity worth of greater than $1.00 must be approved by the SRO.
c.
Any secured experiment with reactivity worth of greater than $2.00 must be approved by the Director.
d.
Any experiment with a reactivity worth that is higher than $0.30 will be moved with a reactor shutdown.
(***** End of Category B *****)
Section C: Facility and Radiation Monitoring Systems QUESTION C.01
[1.0 point]
Which ONE of the following Facility Air Monitor (FAM) channels will monitor for radioactive particulate above the reactor core?
a.
FAM Channel No. 1 b.
FAM Channel No. 2 c.
FAM Channel No. 3 d.
FAM Channel No. 4 QUESTION C.02
[1.0 point]
Which ONE of the following is the neutron startup source?
- a.
Plutonium-Beryllium (Pu-Be)
- b.
Americium-Lithium (Am-Li)
- c.
Antimony-Beryllium (Sb-Be)
- d.
Americium-Beryllium (Am-Be QUESTION C.03
[1.0 point]
For automatic power control, the servo controller automatically maintains power level by comparing the signal from the __________ drawer to a preset signal. It provides a shim-in or shim-out signal to the regulating rod drive controller to adjust power.
a.
Wide Range Linear b.
Log c.
Safety d.
Pulse
Section C: Facility and Radiation Monitoring Systems QUESTION C.04
[1.0 point]
Which ONE of the following conditions will prevent applying air to the Transient Rod (TR) system due to the TR air interlock?
- a.
Pool temperature exceeds 40 °C.
- b.
Reactor is at pulse mode with an initial power at 200 W.
- c.
Air has previously been applied (permissive latch).
- d.
In steady state mode and transient rod drive at its top of travel.
QUESTION C.05
[1.0 point]
Which ONE of the following statements is NOT correct regarding the role of SRO/NSC Director responsibility? (Select the best answer):
a.
The NSC Director or a designated alternate who shall be SROs shall direct any loading or unloading of fuel or control rods within the reactor core region.
b.
The NSC Director or a designated alternate who shall be SROs shall direct any loading or unloading of an in-core experiment with a reactivity worth greater than $1.
c.
The senior reactor operator on duty shall be present at the facility and shall direct the recovery from an unplanned or unscheduled shutdown.
d.
The senior reactor operator on duty shall be present at the facility and shall direct each reactor operation when the power is approaching to 1 MW.
Section C: Facility and Radiation Monitoring Systems QUESTION C.06
[1.0 point]
The attached figure, Figure II-K-2, depicts:
a.
the In-hour Curves b.
the Rod Drop Worth Curves c.
the Period-Differential Worth Curves d.
the Control Rod Scram Time Curves
Section C: Facility and Radiation Monitoring Systems QUESTION C.07
[1.0 point]
Which ONE of the following is the appropriate action if you calculate the reactor excess reactivity of 6.5% K/K during the new core configuration? Assume beta-effective= 0.0076 a.
Reactor can operate not to exceed 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> during the recalculation of excess reactivity.
b.
Reactor can operate but need to inform the Reactor Supervisor for an abnormal condition.
c.
Immediately shutdown the reactor due to exceeding the TS limit.
d.
Reactor can fully operate.
QUESTION C.08
[1.0 point]
The Log Power Channel consists of:
a.
an Uncompensated Ion Chamber and the Safety Drawer.
b.
a Fission Chamber and the Wide Range Linear Monitor.
c.
a Compensated Ion Chamber and the Log Power Monitor.
d.
a Fission Chamber and the Log Power Monitor.
QUESTION C.09
[1.0 point]
Which ONE of the following statements correctly describes the control rod follower?
- a.
All six control rods are fuel followed.
- b.
The four shim safety control rods are poison followed; the transient control rod is void followed, and the regulating rod is fuel followed.
- c.
The four shim safety control rods are fuel followed; the transient control rod is poison followed, and the regulating rod is water followed (no physical follower section).
- d.
The four shim safety control rods are fuel followed; the transient control rod is void (air) followed, and the regulating rod is water followed (no physical follower section).
Section C: Facility and Radiation Monitoring Systems QUESTION C.10
[1.0 point, 0.25 each]
When reactor is at full power, identify the transfer mechanism (Forced Convection, Natural Convection or Conduction) for each of the following:
a.
Cooling the reactor core.
b.
Cooling the pool with the cooling system.
c.
Remove ions by demineralizer.
d.
Exchange of heat between primary and secondary coolant through the heat exchanger.
QUESTION C.11
[1.0 point]
During a reactor operation, you discover the pumps of FAM Channel 2 (monitoring for Fission Product) and FAM Channel 6 (monitoring for Ar-41 in the confinement building) are inoperable.
Other radiation monitors are operating. Which ONE of the following is the best action?
a.
Continue to operate because the pump failure does NOT affect the operations of these monitors.
b.
Continue to operate because the other Radiation Monitors are still working.
c.
Shutdown the reactor; immediately report the result to the supervisor because their failure considers a TS violation.
d Shutdown the reactor, immediately report the result to the U.S. NRC because it is a reportable occurrence.
QUESTION C.12
[1.0 point]
The NSCR fuel element contains:
- a.
a mixture of U-Zr-H alloy with a maximum of 20 weight percent uranium which has a maximum enrichment of 8.5 % U-235.
- b.
a mixture of U-Zn-H alloy with a maximum of 8.5 weight percent uranium which has a maximum enrichment of 20 % U-235.
- c.
a mixture of U-Zr-H alloy with a maximum of 20 weight percent uranium which has a maximum enrichment of 30 % U-235.
- d.
a mixture of U-Zr-H alloy with a maximum of 30 weight percent uranium which has a maximum enrichment of 20 % U-235.
Section C: Facility and Radiation Monitoring Systems QUESTION C.13
[1.0 point]
The reactor operator is conducting the Thermal Power Calibration (Power Calorimetric). Which ONE of the following is an initial setup before recording pool temperature?
a.
Primary water system: ON, Secondary water system: ON, Power level: 40 kW b.
Primary water system: ON, Secondary water system: OFF, Power level: 400 KW c.
Primary water system: OFF, Secondary water system: ON, Power level: 40 kW d.
Primary water system: OFF, Secondary water system: OFF, Power level: 400 kW QUESTION C.14 [1.0 point, 0.25 each]
Match the inputs listed in column A with their responses listed in column B. (Items in column B may be used more than once or not at all). Assume the reactor is in operation.
Column A Column B a.
Log Power =3 mW
- 1.
Indicate only b.
Detector Supply Voltage=100 V 2.
Interlocks c.
Pool water conductivity = 1 micro-mho/cm 3.
Scram d.
Withdrawal of Shim and Transient rods simultaneously in Steady State mode QUESTION C.15
[1.0 point]
Which ONE of the statements best describes the operation of the three-way solenoid valve of the Transient rod air system?
a.
When the solenoid valve de-energized; the vent port is closed. Air flows from pneumatic cylinder back to the accumulator.
b.
When the solenoid valve energized, the supply port is opened, and the actual port is closed. Air from the accumulator is vented through the vent port.
c.
When the solenoid valve is de-energized, the vent (exhaust) port is closed, the supply port is opened, and the actual port (to the cylinder) is opened. Air from the accumulator is continuously supplied to the pneumatic cylinder of the Transient rod.
d.
When the solenoid valve is energized, the vent (exhaust) port is closed, the supply port is opened, and the actual port (to the cylinder) is opened. Air from the accumulator is continuously supplied to the pneumatic cylinder of the Transient rod.
Section C: Facility and Radiation Monitoring Systems QUESTION C.16
[1.0 point]
Which ONE of the following correctly describes the method used to detect radioactivity in the cooling tower if a possible leak in the heat exchanger?
a.
Collect and analyze the cooling tower sample by monthly.
b.
Place a Continuous Air monitor near the cooling tower and check by daily.
c.
Place a radiation area monitor near the cooling tower and check by daily.
d.
Place a radiation area monitor near the heat exchanger and check by weekly.
QUESTION C.17
[1.0 point]
Use the following diagram of an instrumented fuel element. Which ONE of the following is the correct match for the position locator (Column A) to the correct component (Column B)?
Column A Column B I
A. Zirconium Hydride-Uranium II B. Stainless steel III C. Samarium Burnable Poison IV D. Graphite Reflector E. Zirconium Rod F. Spacer G. Thermocouples
- a.
I-C, II-F, III-A, IV-C
- b.
I-D, II-A, III-E, IV-C
- c.
I-D, II-E, III-A, IV-G
- d.
I-C, II-B, III-E, IV-G
Section C: Facility and Radiation Monitoring Systems
Section C: Facility and Radiation Monitoring Systems QUESTION C.18
[1.0 point]
The 3-second period scram signal comes from ________drawer.
a.
Wide Range Linear b.
Log c.
Safety d.
Pulse QUESTION C.19
[1.0 point, 0.25 each]
The Shim rod is continuously rising from 10% to 50% of full length. Select (Open/Closed) for the Limit Switches and (ON/OFF) for the lights. Note: OPEN means the limit switch does NOT activate.
a.
Rod DOWN limit switch (Open/Close) b.
CARR UP limit switch (Open/Close) c.
DOWN light (ON/OFF) d.
ENGAGE light (ON/OFF)
QUESTION C.20
[1.0 point, 0.25 each]
Match the surveillance requirement listed in column A with their appropriate frequency requirement listed in column B. (Items in column B may be used more than once or not at all.)
Column A Column B a.
A channel check of the ARM system
- 1. Each days operation b.
A channel test of the FAM system
- 2. Weekly c.
A channel calibration of the
- 3. Quarterly ARM system d.
Measurement of integrated radiation exposure
- 4. Annually of The environmental monitoring program
(***** END OF CATEGORY C *****)
(***** END OF EXAM *****)
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer:
c
Reference:
= 0.00156 k/k T = (0.0078 - 0.00156)/(0.1*.00156)
T = 40 seconds A.02 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Table2.5, page 2-59.
A.03 Answer:
c
Reference:
P = P0 et/T --> T= t/Ln(P/ P0 )
T= 60/Ln(100 ); T = 13 sec.
A.04 Answer:
b
Reference:
Lamarsh 3rd ed., Section 3.6, page 68-71 Basic Nuclear Engineering 4th ed., Slowing Down of Neutrons, page 226-227 A.05 Answer:
c
Reference:
Burns, R., Introduction to Nuclear Reactor Operations, Example 7.2(b), page 7-4 A.06 Answer:
a
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Sec 2.6 A.07 Answer:
b
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.3.1 A.08 Answer:
b
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, 1988, Table 5.5 A.09 Answer:
c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 8.3 A.10 Answer:
a
Reference:
Burn-up Xe, means adding of a positive reactivity to the core, so you need to insert the control rod to maintain the same power.
eff
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.11 Answer:
c
Reference:
SDM = (1-Keff)/Keff Keff = 1/(SDM + 1) = 1/(.05 + 1) Keff = 0.95 CR1/CR2 = (1 - Keff2) / (1 - Keff1) 400/800 = (1 - Keff2) / (1 - 0.95)
(0.5) x (0.05) = (1 - Keff2)
Keff2 = 1 - (0.5)(0.05) = 0.975 A.12 Answer:
c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 7.7.6 A.13 Answer:
a
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.2.4 A.14 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Sec 3.3.1, page 3-16.
A.15 Answer:
b
Reference:
SCR = (S)/ (1-Keff )
N = (10,000)/(1-0.8) = 50,000 neutrons/second DOE Fundamentals Handbook, NPRT, Vol. 2, Module 4, EO 1.2, p 4 A.16 Answer:
a (3) b (1) c (4) d (2)
(0.25 each)
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 1, Page 43-46 A.17 Answer:
b
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.2 A.18 Answer:
d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.3, page 3-21.
reactor A = (Keff1-Keff2)/(Keff1*Keff2). (0.15-0.1)/(0.15*0.1) = 3.33 k/k reactor B = (Keff1-Keff2)/(Keff1*Keff2). (0.85-0.8)/(0.85*0.8) = 0.0735 k/k 3.33/0.0735 = 45.3 A.19 Answer:
d
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 2.5.3 A.20 Answer:
b
Reference:
DOE Fundamentals Handbook, NPRT, Vol. 2 NP-03, page 34
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer:
a(2);
b(3);
c(3);
d(3)
Reference:
10 CFR 20.1003 Definitions 2 mrem/hr at 1 m = 22.2 mrem/hr at 30 cm => Radiation area 50 mrem/hr at 1m = 0.55 rem/hr at 30 cm => high radiation area 20 mrem/hr at 1m will be equal to 222 mrem/hr at 30 cm :=> high radiation area 4.5 grays 450 rad/hr at 1 m => high radiation area Definition Radiation Area: 5 mrem/hr at 30 cm High Radiation Area: 100 mrem/hr at 30 cm Very High Radiation Area: 500 rads/hr at 1 m B.02 Answer:
a
Reference:
Basic Health Physics B.03 Answer:
d
Reference:
b
Reference:
d
Reference:
10 CFR 55 B.06 Answer:
d
Reference:
10 CFR 20 B.07 Answer:
a (2) b(3) c(1) d(4)
(0.25 each)
Reference:
NRC Standard Question B.08 Answer:
d
Reference:
B.09 Answer:
c
Reference:
DR = DR*e -X Find 150 = 600* e -*40 ; = 0.0346 If insertion of an HVL (thickness of lead), the original intensity will be reduced by half.
Find X: 75 mR/hr = 150 mR/hr* e -0.0346*X ; X= 20 mm Total lead = 20 mm + 40 mm = 60 mm Find HVL by shortcut:
600mR-300 mR is the 1st HVL 300 mR - 150 mR is the 2nd HVL 150- mR - 75 mR is the 3rd HVL
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.10 Answer:
d
Reference:
c
Reference:
- a. = Structure (from Al-27);
- b. = Air;
- c. = Water,
- d. = Fission
Reference:
Standard NRC Question B.13 Answer:
c
Reference:
a
Reference:
b
Reference:
TS Definition, Surveillance Intervals Not exceed: 7.5 months B.16 Answer:
b
Reference:
NSCR TS Definition B.17 Answer:
b
Reference:
a
Reference:
Basic radiation instrumentation B.19 Answer:
c
Reference:
I=6CEn=R/hr@ft.6 x 5 Ci x 0.1Mev x 75% = 2.25 R/hr@ (1ft)2 =
2250 mR/hr = 5 mRem/hr@ D2 = 450 mRem/hr = 21.2 ft.
B.20 Answer:
d
Reference:
NSCR SOP-II-C
C.01 Answer:
b
Reference:
c
Reference:
a
Reference:
d
Reference:
d
Reference:
b
Reference:
NSCR SOP II-K, Control Rod Calibration C.07 Answer:
c
Reference:
d
Reference:
d
Reference:
a = NC; b = FC; c = FC d = Con (0.25 each)
Reference:
Standard NRC questions C.11 Answer:
b
Reference:
d
Reference:
Category B: Normal/Emergency Operating Procedures and Radiological Controls C.13 Answer:
b
Reference:
NSCR SOP Power Calibration C.14 Answer:
a(2) b(3) c(1) d(2)
Reference:
d
Reference:
NSCR TS 7.3.1.1 C.16 Answer:
a
Reference:
c
Reference:
NSCR SAR, Figure 4-9 C.18 Answer:
b
Reference:
a (Open) b(Open) c(OFF) d(ON)
(0.25 each)
Reference:
NRC Standard Question C.20 Answer:
a (1) b(2) c(4) d(3)
(0.25 each)